WorldWideScience

Sample records for safety relevant observations

  1. New conducted electrical weapons: Electrical safety relative to relevant standards.

    Science.gov (United States)

    Panescu, Dorin; Nerheim, Max; Kroll, Mark W; Brave, Michael A

    2017-07-01

    We have previously published about TASER ® conducted electrical weapons (CEW) compliance with international standards. CEWs deliver electrical pulses that can inhibit a person's neuromuscular control or temporarily incapacitate. An eXperimental Rotating-Field (XRF) waveform CEW and the X2 CEW are new 2-shot electrical weapon models designed to target a precise amount of delivered charge per pulse. They both can deploy 1 or 2 dart pairs, delivered by 2 separate cartridges. Additionally, the XRF controls delivery of incapacitating pulses over 4 field vectors, in a rotating sequence. As in our previous study, we were motivated by the need to understand the cardiac safety profile of these new CEWs. The goal of this paper is to analyze the nominal electrical outputs of TASER XRF and X2 CEWs in reference to provisions of all relevant international standards that specify safety requirements for electrical medical devices and electrical fences. Although these standards do not specifically mention CEWs, they are the closest electrical safety standards and hence give very relevant guidance. The outputs of several TASER XRF and X2 CEWs were measured under normal operating conditions. The measurements were compared against manufacturer specifications. CEWs electrical output parameters were reviewed against relevant safety requirements of UL 69, IEC 60335-2-76 Ed 2.1, IEC 60479-1, IEC 60479-2, AS/NZS 60479.1, AS/NZS 60479.2, IEC 60601-1 and BS EN 60601-1. Our study confirmed that the nominal electrical outputs of TASER XRF and X2 CEWs lie within safety bounds specified by relevant standards.

  2. Are classical process safety concepts relevant to nanotechnology applications?

    International Nuclear Information System (INIS)

    Amyotte, Paul R

    2011-01-01

    The answer to the question posed by the title of this paper is yes - with adaptation to the specific hazards and challenges found in the field of nanotechnology. The validity of this affirmative response is demonstrated by relating key process safety concepts to various aspects of the nanotechnology industry in which these concepts are either already practised or could be further applied. This is accomplished by drawing on the current author's experience in process safety practice and education as well as a review of the relevant literature on the safety of nanomaterials and their production. The process safety concepts selected for analysis include: (i) risk management, (ii) inherently safer design, (iii) human error and human factors, (iv) safety management systems, and (v) safety culture.

  3. Nonclinical safety of mavrilimumab, an anti-GMCSF receptor alpha monoclonal antibody, in cynomolgus monkeys: Relevance for human safety

    Energy Technology Data Exchange (ETDEWEB)

    Ryan, Patricia C., E-mail: ryanp@medimmune.com [MedImmune, LLC, Gaithersburg, MD (United States); Sleeman, Matthew A. [MedImmune, LLC, Cambridge (United Kingdom); Rebelatto, Marlon [MedImmune, LLC, Gaithersburg, MD (United States); Wang, Bing; Lu, Hong [MedImmune, LLC, Moutain View, CA (United States); Chen, Xiaomin [Novartis, East Hanover, NJ (United States); Wu, Chi-Yuan [MedImmune, LLC, Moutain View, CA (United States); Hinrichs, Mary Jane; Roskos, Lorin [MedImmune, LLC, Gaithersburg, MD (United States); Towers, Heidi [MedImmune, LLC, Cambridge (United Kingdom); McKeever, Kathleen; Dixit, Rakesh [MedImmune, LLC, Gaithersburg, MD (United States)

    2014-09-01

    Mavrilimumab (CAM-3001) is an investigational human IgG4 monoclonal antibody (MAb) targeting GM-CSF receptor alpha which is currently being developed for the treatment of RA. GM-CSF plays a central role in the pathogenesis of rheumatoid arthritis (RA) through the activation, differentiation, and survival of macrophages and neutrophils. To support clinical development, the nonclinical safety of mavrilimumab was evaluated in several studies with cynomolgus monkeys as the pharmacologically relevant species. Comprehensive toxicity parameters were assessed in each study, and treatment duration ranged from 4 to 26 weeks. Mavrilimumab has an acceptable safety profile in monkeys with no changes in any parameters other than microscopic findings in lung. In several studies, minimal accumulation of foamy alveolar macrophages was observed. This finding was only seen in studies of at least 11 weeks duration, was reversible following a dose-free recovery period and was considered non-adverse. At higher dose levels (≥ 30 mg/kg/week), in a 26-week repeat-IV dose study, the presence of lung foreign material, cholesterol clefts, and granulomatous inflammation was also observed in a few animals and was considered adverse. The dose- and time-related accumulation of foamy macrophages in lung following exposure to mavrilimumab observed in several NHP studies was expected based upon the known role of GM-CSFRα signaling in the function of alveolar macrophages. Overall, a clean no-observed-adverse-effect-level (NOAEL) without any effects in lung was established and provided adequate clinical safety margins. In clinical studies in RA patients, mavrilimumab has demonstrated good clinical activity with adequate safety to support further clinical development. A Phase 2b study of mavrilimumab in subjects with RA is in progress. - Highlights: • Mavrilimumab is a MAB targeting GM-CSFRα being developed for RA therapy. • Mavrilimumab has an acceptable safety profile in cynomolgus monkeys.

  4. Nonclinical safety of mavrilimumab, an anti-GMCSF receptor alpha monoclonal antibody, in cynomolgus monkeys: Relevance for human safety

    International Nuclear Information System (INIS)

    Ryan, Patricia C.; Sleeman, Matthew A.; Rebelatto, Marlon; Wang, Bing; Lu, Hong; Chen, Xiaomin; Wu, Chi-Yuan; Hinrichs, Mary Jane; Roskos, Lorin; Towers, Heidi; McKeever, Kathleen; Dixit, Rakesh

    2014-01-01

    Mavrilimumab (CAM-3001) is an investigational human IgG4 monoclonal antibody (MAb) targeting GM-CSF receptor alpha which is currently being developed for the treatment of RA. GM-CSF plays a central role in the pathogenesis of rheumatoid arthritis (RA) through the activation, differentiation, and survival of macrophages and neutrophils. To support clinical development, the nonclinical safety of mavrilimumab was evaluated in several studies with cynomolgus monkeys as the pharmacologically relevant species. Comprehensive toxicity parameters were assessed in each study, and treatment duration ranged from 4 to 26 weeks. Mavrilimumab has an acceptable safety profile in monkeys with no changes in any parameters other than microscopic findings in lung. In several studies, minimal accumulation of foamy alveolar macrophages was observed. This finding was only seen in studies of at least 11 weeks duration, was reversible following a dose-free recovery period and was considered non-adverse. At higher dose levels (≥ 30 mg/kg/week), in a 26-week repeat-IV dose study, the presence of lung foreign material, cholesterol clefts, and granulomatous inflammation was also observed in a few animals and was considered adverse. The dose- and time-related accumulation of foamy macrophages in lung following exposure to mavrilimumab observed in several NHP studies was expected based upon the known role of GM-CSFRα signaling in the function of alveolar macrophages. Overall, a clean no-observed-adverse-effect-level (NOAEL) without any effects in lung was established and provided adequate clinical safety margins. In clinical studies in RA patients, mavrilimumab has demonstrated good clinical activity with adequate safety to support further clinical development. A Phase 2b study of mavrilimumab in subjects with RA is in progress. - Highlights: • Mavrilimumab is a MAB targeting GM-CSFRα being developed for RA therapy. • Mavrilimumab has an acceptable safety profile in cynomolgus monkeys.

  5. Observational Pharmacoepidemiology in the Drug Safety and Effectiveness Evaluation

    Directory of Open Access Journals (Sweden)

    José Cabrita

    2017-04-01

    Full Text Available Observational epidemiological studies have been used in the medicines context for more than 40 years, contributing to characterize drug use patterns and safety, efficacy and effectiveness profiles. Its use has been increased in recognition of the clinical trials limitations to assess the therapeutic and iatrogenic potential of the medicines after its commercialization. The evolution of the regulatory framework for pharmacovigilance, requiring post-marketing studies, post-authorization safety studies (PASS and the post-authorization efficacy studies (PAES to approve certain drugs, reinforced the importance of observational pharmacoepidemiology for the characterization of the medicines safety and effectiveness profiles. Pharmacoepidemiological research can be carried out from field studies designed to obtain the necessary information or in databases with health records of population samples that already contain the information. This 2nd option is more efficient and more and more frequent. Although, observational research from field studies continues to have its space, the increasing availability of databases allowed a new development to observational pharmacoepidemiology. Indeed, access to automated records databases with up-to-date information on medical prescriptions and global health care to representative population samples with long follow-up periods is a valuable tool for the study of drug use patterns and therapeutic and iatrogenic potential in routine clinical practice. In this context, observational pharmacoepidemiology reinforces its role as a scientific area particularly suitable for evaluating the safety and the effectiveness of the medicines in the “real world”, making a relevant contribution to overcome the gap in translating the evidence from the clinical trials for clinical practice.

  6. Reliability evaluation of the power supply of an electrical power net for safety-relevant applications

    International Nuclear Information System (INIS)

    Dominguez-Garcia, Alejandro D.; Kassakian, John G.; Schindall, Joel E.

    2006-01-01

    In this paper, we introduce a methodology for the dependability analysis of new automotive safety-relevant systems. With the introduction of safety-relevant electronic systems in cars, it is necessary to carry out a thorough dependability analysis of those systems to fully understand and quantify the failure mechanisms in order to improve the design. Several system level FMEAs are used to identify the different failure modes of the system and, a Markov model is constructed to quantify their probability of occurrence. A new power net architecture with application to new safety-relevant automotive systems, such as Steer-by-Wire or Brake-by-Wire, is used as a case study. For these safety-relevant loads, loss of electric power supply means loss of control of the vehicle. It is, therefore, necessary and critical to develop a highly dependable power net to ensure power to these loads under all circumstances

  7. Relevance of microbial finished product testing in food safety management

    DEFF Research Database (Denmark)

    Zwietering, Marcel H.; Jacxsens, Liesbeth; Membré, Jeanne Marie

    2016-01-01

    Management of microbiological food safety is largely based on good design of processes, products and procedures. Finished product testing may be considered as a control measure at the end of the production process. However, testing gives only very limited information on the safety status of a food......-active way by implementing an effective food safety management system. For verification activities in a food safety management system, finished product testing may however be useful. For three cases studies; canned food, chocolate and cooked ham, the relevance of testing both of finished products....... If a hazardous organism is found it means something, but absence in a limited number of samples is no guarantee of safety of a whole production batch. Finished product testing is often too little and too late. Therefore most attention should be focussed on management and control of the hazards in a more pro...

  8. Optimized maintenance concept of safety relevant valves related to ageing management features in nuclear power plants

    International Nuclear Information System (INIS)

    Koring, R.

    2007-01-01

    This paper presents the existing concept in E.ON Kernkraft and its sound application to ageing management issues by focussing on group 2 components such as safety relevant valves. It is demonstrated how the maintenance concept of safety relevant valves is supported by a valve diagnostic system accompanied by an applied procedure to assess the measured results with respect to the required functionality and ageing phenomena. Furthermore this concept has been developed to optimize the existing preventive maintenance of the safety relevant valves by implementing condition oriented aspects derived from the diagnostic results. The main issue of this maintenance concept is to demonstrate the high level of the secured function, reliability and performance of the safety relevant valves within an integrated ageing management. Additionally it offers improvements of all preventive maintenance issues as maintenance periods and the component related volume, spare parts management and costs. (author)

  9. Change detection in urban and rural driving scenes: Effects of target type and safety relevance on change blindness.

    Science.gov (United States)

    Beanland, Vanessa; Filtness, Ashleigh J; Jeans, Rhiannon

    2017-03-01

    The ability to detect changes is crucial for safe driving. Previous research has demonstrated that drivers often experience change blindness, which refers to failed or delayed change detection. The current study explored how susceptibility to change blindness varies as a function of the driving environment, type of object changed, and safety relevance of the change. Twenty-six fully-licenced drivers completed a driving-related change detection task. Changes occurred to seven target objects (road signs, cars, motorcycles, traffic lights, pedestrians, animals, or roadside trees) across two environments (urban or rural). The contextual safety relevance of the change was systematically manipulated within each object category, ranging from high safety relevance (i.e., requiring a response by the driver) to low safety relevance (i.e., requiring no response). When viewing rural scenes, compared with urban scenes, participants were significantly faster and more accurate at detecting changes, and were less susceptible to "looked-but-failed-to-see" errors. Interestingly, safety relevance of the change differentially affected performance in urban and rural environments. In urban scenes, participants were more efficient at detecting changes with higher safety relevance, whereas in rural scenes the effect of safety relevance has marginal to no effect on change detection. Finally, even after accounting for safety relevance, change blindness varied significantly between target types. Overall the results suggest that drivers are less susceptible to change blindness for objects that are likely to change or move (e.g., traffic lights vs. road signs), and for moving objects that pose greater danger (e.g., wild animals vs. pedestrians). Copyright © 2017 Elsevier Ltd. All rights reserved.

  10. The qualification of electrical components and instrumentations relevant to safety

    CERN Document Server

    Zambardi, F

    1989-01-01

    Systems and components relevant to safety of nuclear power plants must maintain their functional integrity in order to assure accident prevention and mitigation. Redundancy is utilized against random failures, nevertheless care must be taken to avoid common failures in redundant components. Main sources of degradation and common cause failures consist in the aging effects and in the changes of environmental conditions which occur during the plant life and the postulated accidents. These causes of degradation are expected to be especially significant for instrumentation and electrical equipment, which can have a primary role in safety systems. The qualification is the methodology by which component safety requirements can be met against the above mentioned causes of degradation. In this report the connection between the possible, plant conditions and the resulting degradation effects on components is preliminarily addressed. A general characterization of the qualification is then presented. Basis, methods and ...

  11. Quantitative software-reliability analysis of computer codes relevant to nuclear safety

    International Nuclear Information System (INIS)

    Mueller, C.J.

    1981-12-01

    This report presents the results of the first year of an ongoing research program to determine the probability of failure characteristics of computer codes relevant to nuclear safety. An introduction to both qualitative and quantitative aspects of nuclear software is given. A mathematical framework is presented which will enable the a priori prediction of the probability of failure characteristics of a code given the proper specification of its properties. The framework consists of four parts: (1) a classification system for software errors and code failures; (2) probabilistic modeling for selected reliability characteristics; (3) multivariate regression analyses to establish predictive relationships among reliability characteristics and generic code property and development parameters; and (4) the associated information base. Preliminary data of the type needed to support the modeling and the predictions of this program are described. Illustrations of the use of the modeling are given but the results so obtained, as well as all results of code failure probabilities presented herein, are based on data which at this point are preliminary, incomplete, and possibly non-representative of codes relevant to nuclear safety

  12. Patient safety challenges in a case study hospital--of relevance for transfusion processes?

    Science.gov (United States)

    Aase, Karina; Høyland, Sindre; Olsen, Espen; Wiig, Siri; Nilsen, Stein Tore

    2008-10-01

    The paper reports results from a research project with the objective of studying patient safety, and relates the finding to safety issues within transfusion medicine. The background is an increased focus on undesired events related to diagnosis, medication, and patient treatment in general in the healthcare sector. The study is designed as a case study within a regional Norwegian hospital conducting specialised health care services. The study includes multiple methods such as interviews, document analysis, analysis of error reports, and a questionnaire survey. Results show that the challenges for improved patient safety, based on employees' perceptions, are hospital management support, reporting of accidents/incidents, and collaboration across hospital units. Several of these generic safety challenges are also found to be of relevance for a hospital's transfusion service. Positive patient safety factors are identified as teamwork within hospital units, a non-punitive response to errors, and unit manager's actions promoting safety.

  13. On safety management and nuclear safety - A frame of reference for studies of safety management with examples from non-nuclear contects of relevance for nuclear safety

    International Nuclear Information System (INIS)

    Svenson, O.; Allwin, P.; Salo, I.

    2004-03-01

    The report includes three case studies of safety management. The studies are presented as chapters, but are written in a format that makes them easy to read separately. Two of the studies cover regulators (the Swedish Civil Aviation Safety Authority, Luftfartsinspektionen) and the Norwegian Petroleum Directorate) and one a regulated activity/industry (a car manufacturer, Volvo Car). The introduction outlines a living system framework and relates this to concepts used in organizational management. The report concludes with some findings with potential relevance for safety management in the nuclear power domain. In the next phase of the work, the regulated counterparts of the regulators here will be investigated in addition to a fourth case study of a regulated activity/industry. (au)

  14. CESAR cost-efficient methods and processes for safety-relevant embedded systems

    CERN Document Server

    Wahl, Thomas

    2013-01-01

    The book summarizes the findings and contributions of the European ARTEMIS project, CESAR, for improving and enabling interoperability of methods, tools, and processes to meet the demands in embedded systems development across four domains - avionics, automotive, automation, and rail. The contributions give insight to an improved engineering and safety process life-cycle for the development of safety critical systems. They present new concept of engineering tools integration platform to improve the development of safety critical embedded systems and illustrate capacity of this framework for end-user instantiation to specific domain needs and processes. They also advance state-of-the-art in component-based development as well as component and system validation and verification, with tool support. And finally they describe industry relevant evaluated processes and methods especially designed for the embedded systems sector as well as easy adoptable common interoperability principles for software tool integratio...

  15. Aspects relevant to safety and environmental protection correlated with nuclear technology

    International Nuclear Information System (INIS)

    Naschi, G.

    1992-01-01

    This paper analyzes the evolution of the most relevant aspects of safety and environmental protection as fundamental elements of the development of nuclear energy in the international framework. The stages leading to the preventive approach to safety in the fifties and in the sixties are also highlighted. During these years, the 'defence in depth' principle was established as the basis for the consequent evolution of the nuclear safety regulations. In this context accident prevention was entrusted to a highly reliable set of redundant systems that could be passive or actuated in a manual or automatic way. In the 1970's, following the accidents of Browns Ferry and Three Mile Island nuclear power plants, an impulse was given to the systematic safety assessment and to the trend of the so-called Probabilistic Risk Assessment (PRA). The paper takes into account the aspects of risk perception as the social effect of Three Mile Island and Chernobyl accidents. This subject has led both to public awareness about the chronic and traumatic risk deriving from a severe accident and, in the international framework, to a process of plants design optimization towards safety and environmental protection. The general aspects of safety and environmental protection are then completed by an overview of the regulatory policies, with particular reference to the licensing procedures developed in Italy

  16. The qualification of electrical components and instrumentations relevant to safety

    International Nuclear Information System (INIS)

    Zambardi, F.

    1989-03-01

    Systems and components relevant to safety of nuclear power plants must maintain their functional integrity in order to assure accident prevention and mitigation. Redundancy is utilized against random failures, nevertheless care must be taken to avoid common failures in redundant components. Main sources of degradation and common cause failures consist in the aging effects and in the changes of environmental conditions which occur during the plant life and the postulated accidents. These causes of degradation are expected to be especially significant for instrumentation and electrical equipment, which can have a primary role in safety systems. The qualification is the methodology by which component safety requirements can be met against the above mentioned causes of degradation. In this report the connection between the possible, plant conditions and the resulting degradation effects on components is preliminarily addressed. A general characterization of the qualification is then presented. Basis, methods and peculiar aspects are discussed and the qualification by testing is taken into special account. Technical and organizational aspects related to a plant qualification program are also focused. The report ends with a look to the most significant research and development activities. (author)

  17. Extended storage for radioactive wastes: relevant aspects related to the safety

    International Nuclear Information System (INIS)

    Castillo, Reinaldo G.; Peralta V, José L.P.; Estevez, Gema G. F.

    2013-01-01

    The safe management of radioactive waste is an issue of great relevance globally linked to the issue of the peaceful use of nuclear energy. Among the steps in the management of this waste, the safe storage is one of the most important. Given the high costs and uncertainties existing among other aspects of the variants of disposal of radioactive waste, the prolonged storage of these wastes for periods exceeding 50 years is an option that different countries more and more value. One of the fundamental problems to take into account is the safety of the stores, so in this work are evaluated different safety components associated with these facilities through a safety analysis methodology. Elements such as human intrusion, the construction site, the design of the facility, among others are identified as some of the key aspects to take into account when evaluating the safety of these types of facilities. Periods of activities planned for a long-term storage of radioactive waste exceed, in general, the useful life of existing storage facilities. This work identified new challenges to overcome in order to meet the requirements for the achievement of a safe management of radioactive waste without negative impacts on the environment and man

  18. Relevant Results of Fish Consumer Benefits and Food Safety

    Directory of Open Access Journals (Sweden)

    Gianita BLEOJU

    2010-12-01

    Full Text Available The paper is focused upon the assessment of current consumer behavior as empirical arguments for designing and implementation of fish feeding and processing innovative biotechnologies which highly meet the exigencies of food safety and security. Recent studies on food consumer behavior are observing the rising awareness of food safety and the reinforcement of the preoccupation about the consequences of healthy diet in terms of prevention and cure as characteristics of life quality. The implications of these changes urge the reconsideration of communication strategy upon food chain in terms of completeness, correctness and continuity of consumer information.

  19. A test of safety, violence prevention, and civility climate domain-specific relationships with relevant workplace hazards.

    Science.gov (United States)

    Gazica, Michele W; Spector, Paul E

    2016-01-01

    Safety climate, violence prevention climate, and civility climate were independently developed and linked to domain-specific workplace hazards, although all three were designed to promote the physical and psychological safety of workers. To test domain specificity between conceptually related workplace climates and relevant workplace hazards. Data were collected from 368 persons employed in various industries and descriptive statistics were calculated for all study variables. Correlational and relative weights analyses were used to test for domain specificity. The three climate domains were similarly predictive of most workplace hazards, regardless of domain specificity. This study suggests that the three climate domains share a common higher order construct that may predict relevant workplace hazards better than any of the scales alone.

  20. Safety relevant failure mechanisms in the post-operational phase

    International Nuclear Information System (INIS)

    Mayer, Gerhard; Stiller, Jan Christopher; Roemer, Sarah

    2017-03-01

    When the 13"t"h amendment of the Atomic Energy Act came into force, eight Germ an nuclear power plant units had their power operating licences revoked and are now in the so-called post operation phase. Of the remaining nuclear power plants, one have by now also entered the post operation phase, with those left in operation bound for entering this phase sometime between now and the end of 2022. Therefore, failure mechanisms that are particularly relevant for post operation were to be identified and described in the frame of the present project. To do so, three major steps were taken: Firstly, recent national and international pertinent literature was evaluated to obtain indications of failure mechanisms in the post operation phase. It turned out that most of the national and international literature deals with the general procedure of the transition from power operation to decommissioning and dismantling. However, there were also some documents providing detailed indications of possible failure mechanisms in post operation. This includes e.g. the release of radioactive materials caused by the drop of containers, chemical impacts on systems important to safety in connection with decontamination work, and corrosion in connection with the storage of the core in the spent fuel pool, with the latter leading to the jamming of the fuel assemblies in the storage racks and a possible reduction of coolant circulation. In a second step, three safety analyses of pressurised water reactors prepared by the respective plant operators were evaluated to identify failure mechanisms based on systems engineering. The failure mechanisms that were found here include e.g. faults in the boric acid concentration of the reactor coolant, damage to the equipment airlock upon the unloading of Castor casks, leakages in connection with primary system decontamination, and the drop of packages holding radioactive residual materials or waste with subsequent mobilisation of radioactive aerosols

  1. Real-Time Emulation of Nonstationary Channels in Safety-Relevant Vehicular Scenarios

    Directory of Open Access Journals (Sweden)

    Golsa Ghiaasi

    2018-01-01

    Full Text Available This paper proposes and discusses the architecture for a real-time vehicular channel emulator capable of reproducing the input/output behavior of nonstationary time-variant radio propagation channels in safety-relevant vehicular scenarios. The vehicular channel emulator architecture aims at a hardware implementation which requires minimal hardware complexity for emulating channels with the varying delay-Doppler characteristics of safety-relevant vehicular scenarios. The varying delay-Doppler characteristics require real-time updates to the multipath propagation model for each local stationarity region. The vehicular channel emulator is used for benchmarking the packet error performance of commercial off-the-shelf (COTS vehicular IEEE 802.11p modems and a fully software-defined radio-based IEEE 802.11p modem stack. The packet error ratio (PER estimated from temporal averaging over a single virtual drive and the packet error probability (PEP estimated from ensemble averaging over repeated virtual drives are evaluated and compared for the same vehicular scenario. The proposed architecture is realized as a virtual instrument on National Instruments™ LabVIEW. The National Instrument universal software radio peripheral with reconfigurable input-output (USRP-Rio 2953R is used as the software-defined radio platform for implementation; however, the results and considerations reported are of general purpose and can be applied to other platforms. Finally, we discuss the PER performance of the modem for two categories of vehicular channel models: a vehicular nonstationary channel model derived for urban single lane street crossing scenario of the DRIVEWAY’09 measurement campaign and the stationary ETSI models.

  2. Current systematic carbon-cycle observations and the need for implementing a policy-relevant carbon observing system

    International Nuclear Information System (INIS)

    Ciais, P.; Peregon, A.; Chevallier, F.; Bopp, L.; Breon, F.M.; Broquet, G.; Luyssaert, S.; Moulin, C.; Paris, J.D.; Poulter, B.; Rivier, L.; Wang, R.

    2014-01-01

    A globally integrated carbon observation and analysis system is needed to improve the fundamental understanding of the global carbon cycle, to improve our ability to project future changes, and to verify the effectiveness of policies aiming to reduce greenhouse gas emissions and increase carbon sequestration. Building an integrated carbon observation system requires transformational advances from the existing sparse, exploratory framework towards a dense, robust, and sustained system in all components: anthropogenic emissions, the atmosphere, the ocean, and the terrestrial biosphere. The paper is addressed to scientists, policy makers, and funding agencies who need to have a global picture of the current state of the (diverse) carbon observations. We identify the current state of carbon observations, and the needs and notional requirements for a global integrated carbon observation system that can be built in the next decade. A key conclusion is the substantial expansion of the ground-based observation networks required to reach the high spatial resolution for CO 2 and CH 4 fluxes, and for carbon stocks for addressing policy-relevant objectives, and attributing flux changes to underlying processes in each region. In order to establish flux and stock diagnostics over areas such as the southern oceans, tropical forests, and the Arctic, in situ observations will have to be complemented with remote-sensing measurements. Remote sensing offers the advantage of dense spatial coverage and frequent revisit. A key challenge is to bring remote-sensing measurements to a level of long-term consistency and accuracy so that they can be efficiently combined in models to reduce uncertainties, in synergy with ground based data. Bringing tight observational constraints on fossil fuel and land use change emissions will be the biggest challenge for deployment of a policy-relevant integrated carbon observation system. This will require in situ and remotely sensed data at much higher

  3. Safety analysis methodology with assessment of the impact of the prediction errors of relevant parameters

    International Nuclear Information System (INIS)

    Galia, A.V.

    2011-01-01

    The best estimate plus uncertainty approach (BEAU) requires the use of extensive resources and therefore it is usually applied for cases in which the available safety margin obtained with a conservative methodology can be questioned. Outside the BEAU methodology, there is not a clear approach on how to deal with the issue of considering the uncertainties resulting from prediction errors in the safety analyses performed for licensing submissions. However, the regulatory document RD-310 mentions that the analysis method shall account for uncertainties in the analysis data and models. A possible approach is presented, that is simple and reasonable, representing just the author's views, to take into account the impact of prediction errors and other uncertainties when performing safety analysis in line with regulatory requirements. The approach proposes taking into account the prediction error of relevant parameters. Relevant parameters would be those plant parameters that are surveyed and are used to initiate the action of a mitigating system or those that are representative of the most challenging phenomena for the integrity of a fission barrier. Examples of the application of the methodology are presented involving a comparison between the results with the new approach and a best estimate calculation during the blowdown phase for two small breaks in a generic CANDU 6 station. The calculations are performed with the CATHENA computer code. (author)

  4. Directly observed road safety compliance by Motor Cycle Riders ...

    African Journals Online (AJOL)

    Objective: To assess the extent of compliance with road safety regulations by motorcycle riders following a five year road safety campaign in Naivasha town, Kenya. Design: A cross sectional study. Setting: Naivasha town, Nakuru county, Kenya. Results: A total of 9,280 MCs ferrying 13,733 people were observed. Less than ...

  5. A review of models relevant to road safety.

    Science.gov (United States)

    Hughes, B P; Newstead, S; Anund, A; Shu, C C; Falkmer, T

    2015-01-01

    It is estimated that more than 1.2 million people die worldwide as a result of road traffic crashes and some 50 million are injured per annum. At present some Western countries' road safety strategies and countermeasures claim to have developed into 'Safe Systems' models to address the effects of road related crashes. Well-constructed models encourage effective strategies to improve road safety. This review aimed to identify and summarise concise descriptions, or 'models' of safety. The review covers information from a wide variety of fields and contexts including transport, occupational safety, food industry, education, construction and health. The information from 2620 candidate references were selected and summarised in 121 examples of different types of model and contents. The language of safety models and systems was found to be inconsistent. Each model provided additional information regarding style, purpose, complexity and diversity. In total, seven types of models were identified. The categorisation of models was done on a high level with a variation of details in each group and without a complete, simple and rational description. The models identified in this review are likely to be adaptable to road safety and some of them have previously been used. None of systems theory, safety management systems, the risk management approach, or safety culture was commonly or thoroughly applied to road safety. It is concluded that these approaches have the potential to reduce road trauma. Copyright © 2014 Elsevier Ltd. All rights reserved.

  6. Observed Food Safety Practices in the Summer Food Service Program

    Science.gov (United States)

    Patten, Emily Vaterlaus; Alcorn, Michelle; Watkins, Tracee; Cole, Kerri; Paez, Paola

    2017-01-01

    Purpose/Objectives: The purpose of this exploratory, observational study was three-fold: 1) Determine current food safety practices at Summer Food Service Program (SFSP) sites; 2) Identify types of food served at the sites and collect associated temperatures; and 3) Establish recommendations for food safety training in the SFSP.…

  7. Contextualizing the global relevance of local land change observations

    International Nuclear Information System (INIS)

    Magliocca, N R; Ellis, E C; Oates, T; Schmill, M

    2014-01-01

    To understand global changes in the Earth system, scientists must generalize globally from observations made locally and regionally. In land change science (LCS), local field-based observations are costly and time consuming, and generally obtained by researchers working at disparate local and regional case-study sites chosen for different reasons. As a result, global synthesis efforts in LCS tend to be based on non-statistical inferences subject to geographic biases stemming from data limitations and fragmentation. Thus, a fundamental challenge is the production of generalized knowledge that links evidence of the causes and consequences of local land change to global patterns and vice versa. The GLOBE system was designed to meet this challenge. GLOBE aims to transform global change science by enabling new scientific workflows based on statistically robust, globally relevant integration of local and regional observations using an online social-computational and geovisualization system. Consistent with the goals of Digital Earth, GLOBE has the capability to assess the global relevance of local case-study findings within the context of over 50 global biophysical, land-use, climate, and socio-economic datasets. We demonstrate the implementation of one such assessment – a representativeness analysis – with a recently published meta-study of changes in swidden agriculture in tropical forests. The analysis provides a standardized indicator to judge the global representativeness of the trends reported in the meta-study, and a geovisualization is presented that highlights areas for which sampling efforts can be reduced and those in need of further study. GLOBE will enable researchers and institutions to rapidly share, compare, and synthesize local and regional studies within the global context, as well as contributing to the larger goal of creating a Digital Earth

  8. Relevant safety issues in designing the HTR-10 reactor

    International Nuclear Information System (INIS)

    Sun Yuliang; Xu Yuanghui

    2001-01-01

    The HTR-10 is a 10 MWth pebble bed high temperature gas cooled reactor being constructed as a research facility at the Institute of Nuclear Energy Technology. This paper discusses design issues of the HTR-10 which are related to safety. It addresses the safety criteria used in the development and assessment of the design, the safety important systems, and the safety classification of components. It also summarises the results of safety analysis, including the approach used for the radioactive source term, as well as the approach to containment design. (author)

  9. On Safety Management. A Frame of Reference for Studies of Safety Management with Examples From Non-Nuclear Contexts of Relevance for Nuclear Safety

    Energy Technology Data Exchange (ETDEWEB)

    Svensson, Ola; Salo, Ilkka; Allwin, Pernilla (Risk Analysis, Social and Decision Research Unit, Dept. of Psychology, Stockholm Univ., Stockholm (Sweden))

    2004-11-15

    A good knowledge about safety management from risk technologies outside the area of nuclear power may contribute to both broaden the perspectives on safety management in general, and point at new opportunities for improving safety measures within the nuclear industry. First, a theoretical framework for the study of safety management in general is presented, followed by three case studies on safety management from different non-nuclear areas with potential relevance for nuclear safety. The chapters are written as separate reports and can be read independently of each other. The nuclear industry has a long experience about the management of risky activities, involving all the stages from planing to implementation, both on a more generalized level and in the specific branches of activities (management, administration, operation, maintenance, etc.). Here, safety management is a key concept related to these areas of activities. Outside the field of nuclear power there exist a number of different non-nuclear risk technologies, each one with their own specific needs and experiences about safety management. The differences between the areas consist partly of the different experiences caused by the different technologies. Besides using own experiences in safety practices within the own areas of activities, it may be profitable to take advantage in knowledge and experiences from one area and put it in practice in another area. In order to facilitate knowledge transfer from one technological area to another it may be possible to adapt a common theoretical model, for descriptions and explanations, to the different technologies. Such a model should admit that common denominators for safety management across the areas might be identified and described with common concepts. Systems theory gives the opportunity to not only create models that are descriptive for events within the limits of a given technology, but also to generate knowledge that can be transferred to other

  10. On Safety Management. A Frame of Reference for Studies of Safety Management with Examples From Non-Nuclear Contexts of Relevance for Nuclear Safety

    International Nuclear Information System (INIS)

    Svensson, Ola; Salo, Ilkka; Allwin, Pernilla

    2004-11-01

    A good knowledge about safety management from risk technologies outside the area of nuclear power may contribute to both broaden the perspectives on safety management in general, and point at new opportunities for improving safety measures within the nuclear industry. First, a theoretical framework for the study of safety management in general is presented, followed by three case studies on safety management from different non-nuclear areas with potential relevance for nuclear safety. The chapters are written as separate reports and can be read independently of each other. The nuclear industry has a long experience about the management of risky activities, involving all the stages from planing to implementation, both on a more generalized level and in the specific branches of activities (management, administration, operation, maintenance, etc.). Here, safety management is a key concept related to these areas of activities. Outside the field of nuclear power there exist a number of different non-nuclear risk technologies, each one with their own specific needs and experiences about safety management. The differences between the areas consist partly of the different experiences caused by the different technologies. Besides using own experiences in safety practices within the own areas of activities, it may be profitable to take advantage in knowledge and experiences from one area and put it in practice in another area. In order to facilitate knowledge transfer from one technological area to another it may be possible to adapt a common theoretical model, for descriptions and explanations, to the different technologies. Such a model should admit that common denominators for safety management across the areas might be identified and described with common concepts. Systems theory gives the opportunity to not only create models that are descriptive for events within the limits of a given technology, but also to generate knowledge that can be transferred to other

  11. Using Total Lightning Observations to Enhance Lightning Safety

    Science.gov (United States)

    Stano, Geoffrey T.

    2012-01-01

    Lightning is often the underrated threat faced by the public when it comes to dangerous weather phenomena. Typically, larger scale events such as floods, hurricanes, and tornadoes receive the vast majority of attention by both the general population and the media. This comes from the fact that these phenomena are large, longer lasting, can impact a large swath of society at one time, and are dangerous events. The threat of lightning is far more isolated on a case by case basis, although millions of cloud-to-ground lightning strikes hit this United States each year. While attention is given to larger meteorological events, lightning is the second leading cause of weather related deaths in the United States. This information raises the question of what steps can be taken to improve lightning safety. Already, the meteorological community s understanding of lightning has increased over the last 20 years. Lightning safety is now better addressed with the National Weather Service s access to the National Lightning Detection Network data and enhanced wording in their severe weather warnings. Also, local groups and organizations are working to improve public awareness of lightning safety with easy phrases to remember, such as "When Thunder Roars, Go Indoors." The impacts can be seen in the greater array of contingency plans, from airports to sports stadiums, addressing the threat of lightning. Improvements can still be made and newer technologies may offer new tools as we look towards the future. One of these tools is a network of sensors called a lightning mapping array (LMA). Several of these networks exist across the United States. NASA s Short-term Prediction Research and Transition Center (SPoRT), part of the Marshall Spaceflight Center, has access to three of these networks from Huntsville, Alabama, the Kennedy Space Center, and Washington D.C. The SPoRT program s mission is to help transition unique products and observations into the operational forecast environment

  12. Towards identification of relevant variables in the observed aerosol optical depth bias between MODIS and AERONET observations

    Science.gov (United States)

    Malakar, N. K.; Lary, D. J.; Gencaga, D.; Albayrak, A.; Wei, J.

    2013-08-01

    Measurements made by satellite remote sensing, Moderate Resolution Imaging Spectroradiometer (MODIS), and globally distributed Aerosol Robotic Network (AERONET) are compared. Comparison of the two datasets measurements for aerosol optical depth values show that there are biases between the two data products. In this paper, we present a general framework towards identifying relevant set of variables responsible for the observed bias. We present a general framework to identify the possible factors influencing the bias, which might be associated with the measurement conditions such as the solar and sensor zenith angles, the solar and sensor azimuth, scattering angles, and surface reflectivity at the various measured wavelengths, etc. Specifically, we performed analysis for remote sensing Aqua-Land data set, and used machine learning technique, neural network in this case, to perform multivariate regression between the ground-truth and the training data sets. Finally, we used mutual information between the observed and the predicted values as the measure of similarity to identify the most relevant set of variables. The search is brute force method as we have to consider all possible combinations. The computations involves a huge number crunching exercise, and we implemented it by writing a job-parallel program.

  13. Evaluation of water-hammer experience in nuclear power plants. Technical findings relevant to Unresolved Safety Issue A-1

    International Nuclear Information System (INIS)

    Serkiz, A.W.

    1983-05-01

    This report summarizes key technical findings relevant to the Unresolved Safety Issue A-1, Water Hammer. These findings were derived from studies of reported water hammer occurrences and underlying causes and provide key insights into means to minimize or eliminate further water hammer occurrences. It should also be noted that this report does not represent a substitute for current rules and regulations

  14. Evaluation of water hammer occurrence in nuclear power plants: technical findings relevant to unresolved safety issue A-1

    International Nuclear Information System (INIS)

    1984-03-01

    This report, which includes responses to public comments, summarizes key technical findings relevant to the Unresolved Safety Issue A-1, Water Hammer. These findings were derived from studies of reported water hammer occurrences and underlying causes and provide key insights into means to minimize or eliminate further water hammer occurrences. This report does not represent a substitute for current rules and regulations

  15. Study on 'Safety qualification of process computers used in safety systems of nuclear power plants'

    International Nuclear Information System (INIS)

    Bertsche, K.; Hoermann, E.

    1991-01-01

    The study aims at developing safety standards for hardware and software of computer systems which are increasingly used also for important safety systems in nuclear power plants. The survey of the present state-of-the-art of safety requirements and specifications for safety-relevant systems and, additionally, for process computer systems has been compiled from national and foreign rules. In the Federal Republic of Germany the KTA safety guides and the BMI/BMU safety criteria have to be observed. For the design of future computer-aided systems in nuclear power plants it will be necessary to apply the guidelines in [DIN-880] and [DKE-714] together with [DIN-192]. With the aid of a risk graph the various functions of a system, or of a subsystem, can be evaluated with regard to their significance for safety engineering. (orig./HP) [de

  16. Encyclopaedic complex of the safety and health protection at the work

    International Nuclear Information System (INIS)

    Anon

    2006-01-01

    This is the encyclopaedia of the safety and health protection at the work. The complex area of the safety and health protection at the work is for the aim of composition of the encyclopaedic composite book latticed into 27 thematic bounded units. The present division enables fast orientation with possibility to focus the attention on observed specific area of work safety. The structure of subject words in thematic units follows the goal totally to cover the actual file of knowledge in relevant area, at which come out form relevant terms, too. The Chapter XXIV deals with ionising and not-ionising radiation

  17. On the use of naturalistic methods to examine safety-relevant behaviours amongst children and evaluate a cycling education program.

    Science.gov (United States)

    Hatfield, J; Dozza, M; Patton, D A; Maharaj, P; Boufous, S; Eveston, T

    2017-11-01

    School-based cycling education programs aim to improve cycling safety and participation amongst children. Available research suggests that typical programs, which focus on bicycle manoeuvring skills, have limited effects on behaviour observed on a track or planned route. The current study uses theoretically more valid, naturalistic cycling data, to evaluate Safe Cycle, a program that incorporates hazard and self-awareness training. Soon after Safe Cycle was delivered at treatment schools, research bicycles instrumented with a rearward- and a forward-facing camera were loaned to six children from treatment schools and six children from (waitlist) control schools. In each group half the children were in Year 6, and half were in Year 7/8. Each child was instructed to ride the research bicycle instead of their own bicycle for the 1-2 weeks that they had a research bicycle. Video data were reduced using a purpose-designed coding scheme that identified whether participants performed specific safety-relevant behaviours in appropriate circumstances. While the participants controlled their bicycles well, gave way appropriately to traffic at intersections, and stopped at red lights, participants frequently removed one or both hands from the handlebars, and seldom signalled turns, conducted over-shoulder-checks when changing lanes, or looked in multiple directions at intersections (except when crossing a road). While aspects of design and small sample sizes limited evaluation findings, this research demonstrated the feasibility and potential of naturalistic data to support cycling education program evaluation. Further, the study substantially extended available naturalistic study of children's cycling behaviour to highlight behaviours which might be targeted by cycling safety initiatives. Copyright © 2017 Elsevier Ltd. All rights reserved.

  18. Work stress and patient safety: observer-rated work stressors as predictors of characteristics of safety-related events reported by young nurses.

    Science.gov (United States)

    Elfering, A; Semmer, N K; Grebner, S

    This study investigates the link between workplace stress and the 'non-singularity' of patient safety-related incidents in the hospital setting. Over a period of 2 working weeks 23 young nurses from 19 hospitals in Switzerland documented 314 daily stressful events using a self-observation method (pocket diaries); 62 events were related to patient safety. Familiarity of safety-related events and probability of recurrence, as indicators of non-singularity, were the dependent variables in multilevel regression analyses. Predictor variables were both situational (self-reported situational control, safety compliance) and chronic variables (job stressors such as time pressure, or concentration demands and job control). Chronic work characteristics were rated by trained observers. The most frequent safety-related stressful events included incomplete or incorrect documentation (40.3%), medication errors (near misses 21%), delays in delivery of patient care (9.7%), and violent patients (9.7%). Familiarity of events and probability of recurrence were significantly predicted by chronic job stressors and low job control in multilevel regression analyses. Job stressors and low job control were shown to be risk factors for patient safety. The results suggest that job redesign to enhance job control and decrease job stressors may be an important intervention to increase patient safety.

  19. Patient safety: Safety culture and patient safety ethics

    DEFF Research Database (Denmark)

    Madsen, Marlene Dyrløv

    2006-01-01

    ,demonstrating significant, consistent and sometimes large differences in terms of safety culture factors across the units participating in the survey. Paper 5 is the results of a study of the relation between safety culture, occupational health andpatient safety using a safety culture questionnaire survey......Patient safety - the prevention of medical error and adverse events - and the initiative of developing safety cultures to assure patients from harm have become one of the central concerns in quality improvement in healthcare both nationally andinternationally. This subject raises numerous...... challenging issues of systemic, organisational, cultural and ethical relevance, which this dissertation seeks to address through the application of different disciplinary approaches. The main focus of researchis safety culture; through empirical and theoretical studies to comprehend the phenomenon, address...

  20. KRISTALLIN-I: estimates of solubility limits for safety relevant radionuclides

    International Nuclear Information System (INIS)

    Berner, U.

    1995-04-01

    The safety concept for the Swiss high level radioactive waste repository is based on a multiple barrier system. Within the concept of the safety analysis KRISTALLIN-I, the waste glass starts corroding after failure of the massive steel canister and nuclides are released to the bentonite backfill. This release is limited by restricted solubility of solid phases. The present work quantifies the maximum expected concentrations of the elements Th, Pa, U, Np, Pu, Am, Cm, Tc, Ni, Pd, Se, Ra, Zr, Nb, Sn, Pb, Sb, Bi and Sm within the reference bentonite porewater with pH = 9, Eh = -400 mV and I = 0.08 M at 50 o C. In a first step, maximum expected concentrations were calculated with a geochemical speciation code (MINEQL) based on a documented thermodynamic database. In a second step, the values obtained in this way were carefully reviewed and modified, based on extended geochemical considerations and system-dependent parameters. Thereby, the relevance of potentially limiting solids, chemical analogies, absolute and relative inventories and recent experimental findings from laboratory and natural systems were particularly considered. The expected groundwater composition in the crystalline host rock (modified by the barrier material bentonite) covers a rather narrow pH range from 8.5 to 9. Within this narrow pH range, solubility limits may be termed as pH independent since computable pH effects are never significant compared to the general uncertainty of the solubility limits. The chemical model defining the reference groundwater predicts a system-wide Eh ranging from -400 mV up to +100 mV. A slightly oxidising near-field will stabilize the generally more soluble higher oxidation states of redox sensitive radionuclides. Based on the available thermodynamic data the elements U, Tc, Se and Pa are predicted not to be solubility limited at +75 mV. Therefore, a more detailed investigation of the redox behaviour of critical elements and, much more importantly, a very careful

  1. Application of FEPs analysis to identify research priorities relevant to the safety case for an Australian radioactive waste facility

    International Nuclear Information System (INIS)

    Payne, T.E.; McGlinn, P.J.

    2007-01-01

    The Australian Nuclear Science and Technology Organisation (ANSTO) has established a project to undertake research relevant to the safety case for the proposed Australian radioactive waste facility. This facility will comprise a store for intermediate level radioactive waste, and either a store or a near-surface repository for low-level waste. In order to identify the research priorities for this project, a structured analysis of the features, events and processes (FEPs) relevant to the performance of the facility was undertaken. This analysis was based on the list of 137 FEPs developed by the IAEA project on 'Safety Assessment Methodologies for Near Surface Disposal Facilities' (ISAM). A number of key research issues were identified, and some factors which differ in significance for the store, compared to the repository concept, were highlighted. For example, FEPs related to long-term groundwater transport of radionuclides are considered to be of less significance for a store than a repository. On the other hand, structural damage from severe weather, accident or human interference is more likely for a store. The FEPs analysis has enabled the scientific research skills required for the inter-disciplinary project team to be specified. The outcomes of the research will eventually be utilised in developing the design, and assessing the performance, of the future facility. It is anticipated that a more detailed application of the FEPs methodology will be undertaken to develop the safety case for the proposed radioactive waste management facility. (authors)

  2. Fundamentals for the safety-relevant design of rotational shiftplans in nuclear power plants

    International Nuclear Information System (INIS)

    Preuss, W.; Herbert, K.W.; Reinartz, G.; Saniter, R.

    1984-01-01

    The investigation was concerned with the influence of rotational shiftwork on operator performance, particularly in the nuclear power industry. In an analysis of the literature, the fundamental chronobiological knowledge was reviewed. Work physiological criteria for the design of shiftplans were assembled and their relevance to this industry was assessed. In addition, interviews were held with representatives from nuclear power utilities in the Federal Republic of Germany and also in Switzerland and the Netherlands. Characteristics of the shiftplans in current use were recorded and the basic operating principles of the shift systems were ascertained. The alternative designs were discussed and assessed from the point of view of operator performance and their significance to safety. The results of the analysis of the literature and of the interviews with the utilities are presented in two separate volumes of the report. (orig.) [de

  3. Culturally Relevant Cyberbullying Prevention

    OpenAIRE

    Phillips, Gregory John

    2017-01-01

    In this action research study, I, along with a student intervention committee of 14 members, developed a cyberbullying intervention for a large urban high school on the west coast. This high school contained a predominantly African American student population. I aimed to discover culturally relevant cyberbullying prevention strategies for African American students. The intervention committee selected video safety messages featuring African American actors as the most culturally relevant cyber...

  4. Safety relevance of vision research and theory.

    NARCIS (Netherlands)

    Koornstra, M.J.

    1993-01-01

    This article discusses the importance of drivers' visual perception to road safety. Evidence is provided to show that the visual perception of a person who is moving at high speed can be seriously affected by both poor visibility and defective eyesight. The point is made that the human eye and mind

  5. Safety evaluation of the NSRR facility relevant to the modification for improved pulse operation and preirradiated fuel experiments

    International Nuclear Information System (INIS)

    Inabe, Teruo; Terakado, Yoshibumi; Tanzawa, Sadamitsu; Katagiri, Hiroshi; Kobayashi, Hideo

    1988-11-01

    The Nuclear Safety Research Reactor (NSRR) is a pulse reactor for the inpile experiments to study the fuel behavior under reactivity initiated accident conditions. The present operation modes of the NSRR consist of the steady state operation up to 300 kW and the natural pulse operation in which a sharp pulsed power is generated from substantially zero power level. In addition to these, two new modes of shaped pulse operation and combined pulse operation will be conducted in the near future as the improved pulse operations. A transient power up to 10 MW will be generated in the shaped pulse operation, and a combination of a transient power up to 10 MW and a sharp pulsed power will be generated in the combined pulse operation. Furthermore, preirradiated fuel rods will be employed in the future experiments whereas the present experiments are confined to the test specimens of unirradiated fuel rods. To provide for these programs, the fundamental design works relevant to the modification of the reactor facility including the reactor instrumentation and control systems and experimental provision were developed. The reactor safety evaluation is prerequisite for confirming the propriety of the fundamental design of the reactor facility from the safety point of view. The safety evaluation was therefore conducted postulating such events that would bring about abnormal conditions in the reactor facility. As a result of the safety evaluation, it has been confirmed as to the NSRR facility after modification that the anticipated transients, the postulated accidents, the major accident and the hypothetical accident do not result respectively in any serious safety problem and that the fundamental design principles and the reactor siting are adequate and acceptable. (author)

  6. Observability-in-depth: An essential complement to the defense-in-depth safety strategy in the nuclear industry

    Energy Technology Data Exchange (ETDEWEB)

    Favaro, Francesca M.; Saleh, Joseph H. [Georgia Institute of Technology, Atlanta (United States)

    2014-12-15

    Defense-in-depth is a fundamental safety principle for the design and operation of nuclear power plants. Despite its general appeal, defense-in-depth is not without its drawbacks, which include its potential for concealing the occurrence of hazardous states in a system, and more generally rendering the latter more opaque for its operators and managers, thus resulting in safety blind spots. This in turn translates into a shrinking of the time window available for operators to identify an unfolding hazardous condition or situation and intervene to abate it. To prevent this drawback from materializing, we propose propose in this work a novel safety principle termed 'observability-in-depth'. We characterize it as the set of provisions technical, operational, and organizational designed to enable the monitoring and identification of emerging hazardous conditions and accident pathogens in real-time and over different time-scales. Observability-in-depth also requires the monitoring of conditions of all safety barriers that implement defense-in-depth; and in so doing it supports sense making of identified hazardous conditions, and the understanding of potential accident sequences that might follow (how they can propagate). Observability-in-depth is thus an information-centric principle, and its importance in accident prevention is in the value of the information it provides and actions or safety interventions it spurs. We examine several 'event reports' from the U.S. Nuclear Regulatory Commission database, which illustrate specific instances of violation of the observability-in-depth safety principle and the consequences that followed (e.g., unmonitored releases and loss of containments). We also revisit the Three Mile Island accident in light of the proposed principle, and identify causes and consequences of the lack of observability-in-depth related to this accident sequence. We illustrate both the benefits of adopting the observability

  7. Relevance of microbial finished product testing in food safety management

    NARCIS (Netherlands)

    Zwietering, M.H.; Jacxsens, L.; Membre, J.M.; Nauta, M.; Peterz, M.

    2016-01-01

    Management of microbiological food safety is largely based on good design of processes, products and procedures. Finished product testing may be considered as a control measure at the end of the production process. However, testing gives only very limited information on the safety status of a food.

  8. OBSERVABILITY-IN-DEPTH: AN ESSENTIAL COMPLEMENT TO THE DEFENSE-IN-DEPTH SAFETY STRATEGY IN THE NUCLEAR INDUSTRY1

    Directory of Open Access Journals (Sweden)

    FRANCESCA M. FAVARÒ

    2014-12-01

    We examine several “event reports” from the U.S. Nuclear Regulatory Commission database, which illustrate specific instances of violation of the observability-in-depth safety principle and the consequences that followed (e.g., unmonitored releases and loss of containments. We also revisit the Three Mile Island accident in light of the proposed principle, and identify causes and consequences of the lack of observability-in-depth related to this accident sequence. We illustrate both the benefits of adopting the observability-in-depth safety principle and the adverse consequences when this principle is violated or not implemented. This work constitutes a first step in the development of the observability-in-depth safety principle, and we hope this effort invites other researchers and safety professionals to further explore and develop this principle and its implementation.

  9. Message maps for safety barrier awareness

    DEFF Research Database (Denmark)

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

    2011-01-01

    , time, or place, and by enabling them to observe and judge whether the relevant safety barriers are in place and in good order. This can be considered “Situational Awareness” (SA), which is an essential competence enabling an employee to perform his/her job safely. This SA entails a number...... of requirements for people, work conditions, management, learning, knowledge, experience, motivation etc. The Dutch WORM and RAM projects led to the identification of 64 types of risks and the safety barriers and performance factors linked to these risks. The Danish DanWORM project has transferred this knowledge...

  10. Message maps for Safety Barrier Awareness

    DEFF Research Database (Denmark)

    of the risks in a given situation, time or place, and by enabling them to observe and judge whether the relevant safety barriers are in place and in good order. This can be considered as “Situational Awareness (SA)”, which is an essential competence for at en employee can perform his/her job safely....... This Situational Awareness puts a number of requirements on people, work conditions, management, learning, knowledge, experience, motivation, etc. The Dutch WORM and RAM projects led to the identification of 64 types of risks and the safety barriers and performance factors that are linked to these risks...

  11. Theories of risk and safety: what is their relevance to nursing?

    Science.gov (United States)

    Cooke, Hannah

    2009-03-01

    The aim of this paper is to review key theories of risk and safety and their implications for nursing. The concept of of patient safety has only recently risen to prominence as an organising principle in healthcare. The paper considers the wider social context in which contemporary concepts of risk and safety have developed. In particular it looks at sociological debates about the rise of risk culture and the risk society and their influence on the patient safety movement. The paper discusses three bodies of theory which have attempted to explain the management of risk and safety in organisations: normal accident theory, high reliability theory, and grid-group cultural theory. It examine debates between these theories and their implications for healthcare. It discusses reasons for the dominance of high reliability theory in healthcare and its strengths and limitations. The paper suggest that high reliability theory has particular difficulties in explaining some aspects of organisational culture. It also suggest that the implementation of high reliability theory in healthcare has involved over reliance on numerical indicators. It suggests that patient safety could be improved by openness to a wider range of theoretical perspectives.

  12. Safety balance: Analysis of safety systems

    International Nuclear Information System (INIS)

    Delage, M.; Giroux, C.

    1990-12-01

    Safety analysis, and particularly analysis of exploitation of NPPs is constantly affected by EDF and by the safety authorities and their methodologies. Periodic safety reports ensure that important issues are not missed on daily basis, that incidents are identified and that relevant actions are undertaken. French safety analysis method consists of three principal steps. First type of safety balance is analyzed at the normal start-up phase for each unit including the final safety report. This enables analysis of behaviour of units ten years after their licensing. Second type is periodic operational safety analysis performed during a few years. Finally, the third step consists of safety analysis of the oldest units with the aim to improve the safety standards. The three steps of safety analysis are described in this presentation in detail with the aim to present the objectives and principles. Examples of most recent exercises are included in order to illustrate the importance of such analyses

  13. Safety relevant failure mechanisms in the post-operational phase; Sicherheitstechnisch relevante Fehlermechanismen in der Nachbetriebsphase

    Energy Technology Data Exchange (ETDEWEB)

    Mayer, Gerhard; Stiller, Jan Christopher; Roemer, Sarah

    2017-03-15

    When the 13{sup th} amendment of the Atomic Energy Act came into force, eight Germ an nuclear power plant units had their power operating licences revoked and are now in the so-called post operation phase. Of the remaining nuclear power plants, one have by now also entered the post operation phase, with those left in operation bound for entering this phase sometime between now and the end of 2022. Therefore, failure mechanisms that are particularly relevant for post operation were to be identified and described in the frame of the present project. To do so, three major steps were taken: Firstly, recent national and international pertinent literature was evaluated to obtain indications of failure mechanisms in the post operation phase. It turned out that most of the national and international literature deals with the general procedure of the transition from power operation to decommissioning and dismantling. However, there were also some documents providing detailed indications of possible failure mechanisms in post operation. This includes e.g. the release of radioactive materials caused by the drop of containers, chemical impacts on systems important to safety in connection with decontamination work, and corrosion in connection with the storage of the core in the spent fuel pool, with the latter leading to the jamming of the fuel assemblies in the storage racks and a possible reduction of coolant circulation. In a second step, three safety analyses of pressurised water reactors prepared by the respective plant operators were evaluated to identify failure mechanisms based on systems engineering. The failure mechanisms that were found here include e.g. faults in the boric acid concentration of the reactor coolant, damage to the equipment airlock upon the unloading of Castor casks, leakages in connection with primary system decontamination, and the drop of packages holding radioactive residual materials or waste with subsequent mobilisation of radioactive aerosols

  14. Technological Advances in Cardiovascular Safety Assessment Decrease Preclinical Animal Use and Improve Clinical Relevance.

    Science.gov (United States)

    Berridge, Brian R; Schultze, A Eric; Heyen, Jon R; Searfoss, George H; Sarazan, R Dustan

    2016-12-01

    Cardiovascular (CV) safety liabilities are significant concerns for drug developers and preclinical animal studies are predominately where those liabilities are characterized before patient exposures. Steady progress in technology and laboratory capabilities is enabling a more refined and informative use of animals in those studies. The application of surgically implantable and telemetered instrumentation in the acute assessment of drug effects on CV function has significantly improved historical approaches that involved anesthetized or restrained animals. More chronically instrumented animals and application of common clinical imaging assessments like echocardiography and MRI extend functional and in-life structural assessments into the repeat-dose setting. A growing portfolio of circulating CV biomarkers is allowing longitudinal and repeated measures of cardiac and vascular injury and dysfunction better informing an understanding of temporal pathogenesis and allowing earlier detection of undesirable effects. In vitro modeling systems of the past were limited by their lack of biological relevance to the in vivo human condition. Advances in stem cell technology and more complex in vitro modeling platforms are quickly creating more opportunity to supplant animals in our earliest assessments for liabilities. Continuing improvement in our capabilities in both animal and nonanimal modeling should support a steady decrease in animal use for primary liability identification and optimize the translational relevance of the animal studies we continue to do. © The Author 2016. Published by Oxford University Press on behalf of the Institute for Laboratory Animal Research. All rights reserved. For permissions, please email: journals.permissions@oup.com.

  15. Fundamental safety principles. Safety fundamentals

    International Nuclear Information System (INIS)

    2007-01-01

    This publication states the fundamental safety objective and ten associated safety principles, and briefly describes their intent and purpose. The fundamental safety objective - to protect people and the environment from harmful effects of ionizing radiation - applies to all circumstances that give rise to radiation risks. The safety principles are applicable, as relevant, throughout the entire lifetime of all facilities and activities - existing and new - utilized for peaceful purposes, and to protective actions to reduce existing radiation risks. They provide the basis for requirements and measures for the protection of people and the environment against radiation risks and for the safety of facilities and activities that give rise to radiation risks, including, in particular, nuclear installations and uses of radiation and radioactive sources, the transport of radioactive material and the management of radioactive waste

  16. Fundamental safety principles. Safety fundamentals

    International Nuclear Information System (INIS)

    2006-01-01

    This publication states the fundamental safety objective and ten associated safety principles, and briefly describes their intent and purpose. The fundamental safety objective - to protect people and the environment from harmful effects of ionizing radiation - applies to all circumstances that give rise to radiation risks. The safety principles are applicable, as relevant, throughout the entire lifetime of all facilities and activities - existing and new - utilized for peaceful purposes, and to protective actions to reduce existing radiation risks. They provide the basis for requirements and measures for the protection of people and the environment against radiation risks and for the safety of facilities and activities that give rise to radiation risks, including, in particular, nuclear installations and uses of radiation and radioactive sources, the transport of radioactive material and the management of radioactive waste

  17. Incorporating organisational safety culture within ergonomics practice.

    Science.gov (United States)

    Bentley, Tim; Tappin, David

    2010-10-01

    This paper conceptualises organisational safety culture and considers its relevance to ergonomics practice. Issues discussed in the paper include the modest contribution that ergonomists and ergonomics as a discipline have made to this burgeoning field of study and the significance of safety culture to a systems approach. The relevance of safety culture to ergonomics work with regard to the analysis, design, implementation and evaluation process, and implications for participatory ergonomics approaches, are also discussed. A potential user-friendly, qualitative approach to assessing safety culture as part of ergonomics work is presented, based on a recently published conceptual framework that recognises the dynamic and multi-dimensional nature of safety culture. The paper concludes by considering the use of such an approach, where an understanding of different aspects of safety culture within an organisation is seen as important to the success of ergonomics projects. STATEMENT OF RELEVANCE: The relevance of safety culture to ergonomics practice is a key focus of this paper, including its relationship with the systems approach, participatory ergonomics and the ergonomics analysis, design, implementation and evaluation process. An approach to assessing safety culture as part of ergonomics work is presented.

  18. [Roadside observation on the use of safety belt in Guangzhou and Nanning cites of China].

    Science.gov (United States)

    Li, Li-ping; Stevenson, Mark; Ivers, Rebecca; Zhou, Ying

    2006-08-01

    To determine the rates of correct use of safety belt (CUSB) among drivers and front seat passengers in Guangzhou and Nanning through roadside observation and to provide scientific evidence for the development of intervention plan and to strengthen road safety law enforcement. Observational sites were randomly selected from three road types (Highway, Main Street and Subordinate Street). Targeted automobiles were observed at each site at four different times and uniformed checklists were used to record safety belt use during observations. Within each vehicle, belt use by drivers of different sex, road type, workday/weekend, day/night and seating position were calculated. Data was analyzed, using Chi-square tests to compare the statistic significance. (1)The rate of CUSB and non-use rate among drivers were higher in Nanning than in Guangzhou (P= 0.00) but the rate of incorrect use was on the contrarary. (2) The rate of CUSB by front seat passengers in Guangzhou was higher than that in Nanning (P = 0.04); as well as the rate of (P = 0.00) incorrect use while the non-use rate was on the contrarary. (3)In general, the rate of CUSB was higher on highways than on local streets (P = 0.00). (4) The CUSB rate of drivers and front seat passengers was higher at daytime than at night (P = 0.00), and the rate of incorrect use was higher at working days than weekends (P = 0.00). (5) The CUSB rate was higher for female drivers than for males in Guangzhou (P = 0.00), but there no statistical significance was found in Nanning (P = 0.21). Results suggested that intervention actions should be undertaken to raise the awareness of the importance of safety belt use. Effective public information and education programs, law enforcement and mandatory safety belt use, prioritizing programs on people neglegent to the importance are necessary to increase the safety belt use and to decrease the mortality and injuries caused by traffic accidents.

  19. Topical session proceedings of the 5. IGSC meeting on: observations regarding the safety case in recent safety assessment studies

    International Nuclear Information System (INIS)

    Hooper, Alan J.; Voinis, Sylvie; Van Luik, Abraham E.

    2004-01-01

    Within the NEA, the IGSC (Integration Group for the Safety Case) has, as an essential role, to develop common views on such key aspects of the safety case. Therefore, since the inauguration of the IGSC in 2000, four meetings were organised with topical sessions to explore various of these key aspects. This is a report on the fifth such topical session, held as part of the 5. plenary meeting of the IGSC. The session was attended by 36 participants, representing waste management organisations and regulatory authorities from 16 NEA member countries, the IAEA and the European Commission. The purpose of this topical session was to provide support to the finalising of the IGSC safety case brochure by getting a description of the safety case content of the IAEA Draft Safety Requirements document and by getting an overview of progress that could be observed from national organisations on developing their cases for system safety and/or developing the required methodologies. The objective was that the IGSC safety case brochure should be supportive of the IAEA/NEA document, and be reflective of the experience of the IGSC member programmes and organisations. The topical session was mainly aimed at exchanging information on: - The safety case related content of the proposed IAEA/NEA document (currently titled: 'IAEA Safety Standards Series, Geological Disposal of Radioactive Waste, Draft Safety Requirements (DS-154)'). - National programmes where safety assessments have recently been completed, e.g. ONDRAF/NIRAS, Nagra and Andra. - Feedback from international peer reviews, e.g. the Andra Dossier 2001 Argile, the Belgian SAFIR 2 report, the SR 97 report and the US-DOE Yucca Mountain TSPA. - The evolution of some national assessment methods and approaches e.g. SKB and Nagra. - The content of the draft IGSC safety case brochure entitled: 'The Nature and Purpose of the Post-closure Safety Case in Geological Disposal'. This document presents the various

  20. Safety Review related to Commercial Grade Digital Equipment in Safety System

    International Nuclear Information System (INIS)

    Yu, Yeongjin; Park, Hyunshin; Yu, Yeongjin; Lee, Jaeheung

    2013-01-01

    The upgrades or replacement of I and C systems on safety system typically involve digital equipment developed in accordance with non-nuclear standards. However, the use of commercial grade digital equipment could include the vulnerability for software common-mode failure, electromagnetic interference and unanticipated problems. Although guidelines and standards for dedication methods of commercial grade digital equipment are provided, there are some difficulties to apply the methods to commercial grade digital equipment for safety system. This paper focuses on regulatory guidelines and relevant documents for commercial grade digital equipment and presents safety review experiences related to commercial grade digital equipment in safety system. This paper focuses on KINS regulatory guides and relevant documents for dedication of commercial grade digital equipment and presents safety review experiences related to commercial grade digital equipment in safety system. Dedication including critical characteristics is required to use the commercial grade digital equipment on safety system in accordance with KEPIC ENB 6370 and EPRI TR-106439. The dedication process should be controlled in a configuration management process. Appropriate methods, criteria and evaluation result should be provided to verify acceptability of the commercial digital equipment used for safety function

  1. Introduction to safety theory

    International Nuclear Information System (INIS)

    Meyna, A.

    1982-01-01

    After a general introduction to safety theory, safety characteristics are defined and quantified. This is followed by a calculation of the safety characteristics of simple, safety-relevant systems in general and in consideration of common-mode errors. The qualitative and quantitative role of human errors is discussed for various models, and a simple man-machine model is developed for investigation of common-mode errors and human error. The main part of the paper deals with safety analysis in complex systems. After a general review, the common inductive and deductive methods of analysis are presented and commented on and their fields of application discussed. Analytical and simulation codes are presented as methods of evaluation for big, complex event trees - i.e. ''hazard trees in the sense of safety engineering (as a subset of safety relevance). After a basic classification and mathematical formulation of Markovian processes, the author shows that these may be used successfully for calculation of safety characteristics if transition rates are constant and if the number of system states is limited. (orig./RW) [de

  2. Increased earthquake safety through optimised mounting concept

    International Nuclear Information System (INIS)

    Kollmann, Dieter; Senechal, Holger

    2013-01-01

    Since Fukushima, there has been intensive work on earthquake safety in all nuclear power plants. A large part of these efforts aim at the earthquake safety of safety-relevant pipeline systems. The problem with earthquake safety here is not the pipeline system itself but rather its mountings and connections to components. This is precisely the topic that the KAE dealt with in years of research and development work. It has developed an algorithm that determines the optimal mounting concept with a few iteration steps depending on arbitrary combinations of loading conditions whilst maintaining compliance with relevant regulations for any pipeline systems. With this tool at hand, we are now in a position to plan and realise remedial measures accurately with minimum time and hardware expenditure, and so distinctly improve the earthquake safety of safety-relevant systems. (orig.)

  3. Laser cutting: industrial relevance, process optimization, and laser safety

    Science.gov (United States)

    Haferkamp, Heinz; Goede, Martin; von Busse, Alexander; Thuerk, Oliver

    1998-09-01

    Compared to other technological relevant laser machining processes, up to now laser cutting is the application most frequently used. With respect to the large amount of possible fields of application and the variety of different materials that can be machined, this technology has reached a stable position within the world market of material processing. Reachable machining quality for laser beam cutting is influenced by various laser and process parameters. Process integrated quality techniques have to be applied to ensure high-quality products and a cost effective use of the laser manufacturing plant. Therefore, rugged and versatile online process monitoring techniques at an affordable price would be desirable. Methods for the characterization of single plant components (e.g. laser source and optical path) have to be substituted by an omnivalent control system, capable of process data acquisition and analysis as well as the automatic adaptation of machining and laser parameters to changes in process and ambient conditions. At the Laser Zentrum Hannover eV, locally highly resolved thermographic measurements of the temperature distribution within the processing zone using cost effective measuring devices are performed. Characteristic values for cutting quality and plunge control as well as for the optimization of the surface roughness at the cutting edges can be deducted from the spatial distribution of the temperature field and the measured temperature gradients. Main influencing parameters on the temperature characteristic within the cutting zone are the laser beam intensity and pulse duration in pulse operation mode. For continuous operation mode, the temperature distribution is mainly determined by the laser output power related to the cutting velocity. With higher cutting velocities temperatures at the cutting front increase, reaching their maximum at the optimum cutting velocity. Here absorption of the incident laser radiation is drastically increased due to

  4. MAXimising Involvement in MUltiMorbidity (MAXIMUM) in primary care: protocol for an observation and interview study of patients, GPs and other care providers to identify ways of reducing patient safety failures.

    Science.gov (United States)

    Daker-White, Gavin; Hays, Rebecca; Esmail, Aneez; Minor, Brian; Barlow, Wendy; Brown, Benjamin; Blakeman, Thomas; Bower, Peter

    2014-08-18

    Increasing numbers of older people are living with multiple long-term health conditions but global healthcare systems and clinical guidelines have traditionally focused on the management of single conditions. Having two or more long-term conditions, or 'multimorbidity', is associated with a range of adverse consequences and poor outcomes and could put patients at increased risk of safety failures. Traditionally, most research into patient safety failures has explored hospital or inpatient settings. Much less is known about patient safety failures in primary care. Our core aims are to understand the mechanisms by which multimorbidity leads to safety failures, to explore the different ways in which patients and services respond (or fail to respond), and to identify opportunities for intervention. We plan to undertake an applied ethnographic study of patients with multimorbidity. Patients' interactions and environments, relevant to their healthcare, will be studied through observations, diary methods and semistructured interviews. A framework, based on previous studies, will be used to organise the collection and analysis of field notes, observations and other qualitative data. This framework includes the domains: access breakdowns, communication breakdowns, continuity of care errors, relationship breakdowns and technical errors. Ethical approval was received from the National Health Service Research Ethics Committee for Wales. An individual case study approach is likely to be most fruitful for exploring the mechanisms by which multimorbidity leads to safety failures. A longitudinal and multiperspective approach will allow for the constant comparison of patient, carer and healthcare worker expectations and experiences related to the provision, integration and management of complex care. This data will be used to explore ways of engaging patients and carers more in their own care using shared decision-making, patient empowerment or other relevant models. Published by

  5. Fall prevention and safety communication training for foremen: report of a pilot project designed to improve residential construction safety.

    Science.gov (United States)

    Kaskutas, Vicki; Dale, Ann Marie; Lipscomb, Hester; Evanoff, Brad

    2013-02-01

    Falls from heights account for 64% of residential construction worker fatalities and 20% of missed work days. We hypothesized that worker safety would improve with foremen training in fall prevention and safety communication. Training priorities identified through foreman and apprentice focus groups and surveys were integrated into an 8-hour training. We piloted the training with ten foremen employed by a residential builder. Carpenter trainers contrasted proper methods to protect workers from falls with methods observed at the foremen's worksites. Trainers presented methods to deliver toolbox talks and safety messages. Results from worksite observational audits (n=29) and foremen/crewmember surveys (n=97) administered before and after training were compared. We found that inexperienced workers are exposed to many fall hazards that they are often not prepared to negotiate. Fall protection is used inconsistently and worksite mentorship is often inadequate. Foremen feel pressured to meet productivity demands and some are unsure of the fall protection requirements. After the training, the frequency of daily mentoring and toolbox talks increased, and these talks became more interactive and focused on hazardous daily work tasks. Foremen observed their worksites for fall hazards more often. We observed increased compliance with fall protection and decreased unsafe behaviors during worksite audits. Designing the training to meet both foremen's and crewmembers' needs ensured the training was learner-centered and contextually-relevant. This pilot suggests that training residential foremen can increase use of fall protection, improve safety behaviors, and enhance on-the-job training and safety communication at their worksites. Construction workers' training should target safety communication and mentoring skills with workers who will lead work crews. Interventions at multiple levels are necessary to increase safety compliance in residential construction and decrease falls

  6. Tensile and burst tests in support of the cadmium safety rod failure evaluation

    International Nuclear Information System (INIS)

    Thomas, J.K.

    1992-02-01

    The reactor safety rods may be subjected to high temperatures due to gamma heating after the core coolant level has dropped during the ECS phase of hypothetical LOCA event. Accordingly, an experimental safety rod testing subtask was established as part of a task to address the response of reactor core components to this accident. This report discusses confirmatory separate effects tests conducted to support the evaluation of failures observed in the safety rod thermal tests. As part of the failure evaluation, the potential for liquid metal embrittlement (LME) of the safety rod cladding by cadmium (Cd) -- aluminum (Al) solutions was examined. Based on the test conditions, literature data, and U-Bend tests, its was concluded that the SS304 safety rod cladding would not be subject to LME by liquid Cd-Al solutions under conditions relevant to the safety rod thermal tests or gamma heating accident. To confirm this conclusion, tensile tests on SS304 specimens were performed in both air and liquid Cd-Al solutions with the range of strain rates, temperatures, and loading conditions spanning the range relevant to the safety rod thermal tests and gamma heating accident

  7. Design and evaluation of simulation scenarios for a program introducing patient safety, teamwork, safety leadership, and simulation to healthcare leaders and managers.

    Science.gov (United States)

    Cooper, Jeffrey B; Singer, Sara J; Hayes, Jennifer; Sales, Michael; Vogt, Jay W; Raemer, Daniel; Meyer, Gregg S

    2011-08-01

    We developed a training program to introduce managers and informal leaders of healthcare organizations to key concepts of teamwork, safety leadership, and simulation to motivate them to act as leaders to improve safety within their sphere of influence. This report describes the simulation scenario and debriefing that are core elements of that program. Twelve teams of clinician and nonclinician managers were selected from a larger set of volunteers to participate in a 1-day, multielement training program. Two simulation exercises were developed: one for teams of nonclinicians and the other for clinicians or mixed groups. The scenarios represented two different clinical situations, each designed to engage participants in discussions of their safety leadership and teamwork issues immediately after the experience. In the scenarios for nonclinicians, participants conducted an anesthetic induction and then managed an ethical situation. The scenario for clinicians simulated a consulting visit to an emergency room that evolved into a problem-solving challenge. Participants in this scenario had a limited time to prepare advice for hospital leadership on how to improve observed safety and cultural deficiencies. Debriefings after both types of scenarios were conducted using principles of "debriefing with good judgment." We assessed the relevance and impact of the program by analyzing participant reactions to the simulation through transcript data and facilitator observations as well as a postcourse questionnaire. The teams generally reported positive perceptions of the relevance and quality of the simulation with varying types and degrees of impact on their leadership and teamwork behaviors. These kinds of clinical simulation exercises can be used to teach healthcare leaders and managers safety leadership and teamwork skills and behaviors.

  8. Twenty sixth DAE safety and occupational health professionals meet: cryogenic safety, electrical safety and ergonomics at work place

    International Nuclear Information System (INIS)

    2009-01-01

    This conference gathered knowledge in safety and occupational health hazards in various fields of nuclear science and technology like radiations, high voltages, ultra-low temperature, ultra-high magnetic fields, electrical breakdown, fire, ergonomics and cryogenic safety at work place. Papers relevant to INIS database are indexed separately

  9. Observational Studies on Evaluating the Safety and Adverse Effects of Traditional Chinese Medicine

    Directory of Open Access Journals (Sweden)

    Jung-Nein Lai

    2013-01-01

    Full Text Available Background. This study aims to share our experiences when carrying out observational studies of traditional Chinese medicine (TCM. Methods. We have proactively monitored the safety profiles of Duhuo Jisheng Tang (DJT, Suan Zao Ren Tang (SZRT, and TMN-1. A list of adverse events (AEs, complete blood counts, and liver and kidney function tests were obtained from the participants during their scheduled hospital visits. Retrospective observational studies were conducted based on the reimbursement database of the National Health Insurance system, Taiwan, to explore the relationship between the use of TCM that have been adulterated by aristolochic acid and the risk from both nephrotoxins and carcinogens. Results. A total of 221, 287, and 203 AEs were detected after SZRT, DJT, and TMN-1 had been taken, respectively. Dizziness, headache, stomach ache, and diarrhea were judged to be probably related to SZRT treatment. Retrospective observational studies found an association between the consumption of aristolochic acid-containing Chinese formulae such as Mu Tong and an increased risk of CKD, ESRD, and urinary tract cancer. Conclusion. Prospective and retrospective observational studies seem to have specific advantages when investigating the safety and adverse effects of TCM therapies, as well as possibly other alternative/complementary therapies.

  10. Observational Studies on Evaluating the Safety and Adverse Effects of Traditional Chinese Medicine

    Science.gov (United States)

    Tang, Jin-Ling; Wang, Jung-Der

    2013-01-01

    Background. This study aims to share our experiences when carrying out observational studies of traditional Chinese medicine (TCM). Methods. We have proactively monitored the safety profiles of Duhuo Jisheng Tang (DJT), Suan Zao Ren Tang (SZRT), and TMN-1. A list of adverse events (AEs), complete blood counts, and liver and kidney function tests were obtained from the participants during their scheduled hospital visits. Retrospective observational studies were conducted based on the reimbursement database of the National Health Insurance system, Taiwan, to explore the relationship between the use of TCM that have been adulterated by aristolochic acid and the risk from both nephrotoxins and carcinogens. Results. A total of 221, 287, and 203 AEs were detected after SZRT, DJT, and TMN-1 had been taken, respectively. Dizziness, headache, stomach ache, and diarrhea were judged to be probably related to SZRT treatment. Retrospective observational studies found an association between the consumption of aristolochic acid-containing Chinese formulae such as Mu Tong and an increased risk of CKD, ESRD, and urinary tract cancer. Conclusion. Prospective and retrospective observational studies seem to have specific advantages when investigating the safety and adverse effects of TCM therapies, as well as possibly other alternative/complementary therapies. PMID:24159351

  11. Stennis Space Center observes 2009 Safety and Health Day

    Science.gov (United States)

    2009-01-01

    Sue Smith, a medical clinic employee at NASA's John C. Stennis Space Center, takes the temperature of colleague Karen Badon during 2009 Safety and Health Day activities Oct. 22. Safety Day activities included speakers, informational sessions and a number of displays on safety and health issues. Astronaut Dominic Gorie also visited the south Mississippi rocket engine testing facility during the day to address employees and present several Silver Snoopy awards for outstanding contributions to flight safety and mission success. The activities were part of an ongoing safety and health emphasis at Stennis.

  12. Relevance of nanotechnology to Africa: synthesis, applications and safety

    CSIR Research Space (South Africa)

    Musee, N

    2012-07-01

    Full Text Available In this chapter, two nanotechnology-based applications relevant to Africa in promoting sustainability and achievement of the Millennium Development Goals (MDGs) are presented. The applications comprise the provision of therapeutic treatment...

  13. China's Work Safety Report

    Institute of Scientific and Technical Information of China (English)

    Liang Jiakun

    2005-01-01

    @@ General Situation of China's Work Safety in 2004 In 2004, the national work safety situation remained stable as a whole and gained momentum to improve. The totality of accidents held the line and began to drop. The safety conditions in industrial,mining, and commercial/trading enterprises improved. Progress was made in ensuring work safety in the relevant industries and fields. The safety situation in most provinces (autonomous regions, municipalities directly under the Central Government) kept stable.

  14. Influence of shock waves as a result of assumed vessel failure on parts of the plant relevant to safety

    International Nuclear Information System (INIS)

    Danisch, R.; Graubner, U.

    1981-01-01

    The shock wave induced rupture is of subordinate importance for the laying out of the parts of the plant relevant to safety. It is covered by the precautions for maximum potential earthquakes, aircraft crashes and chemical explosions. The failure of vessels in the power house (WAZUe, SPWB) as the result of a maximum potential earthquake is extremely improbable. If a combination of the stresses resulting from maximum potential earthquakes with the hypothetical stresses resulting from vessel failure is undertaken, it can be seen that the total stresses are only increased by a minimal amount, due to the quadratic averaging of less than 3%. (orig./DG) [de

  15. Current Activities on Nuclear Safety Culture in Korea. How to meet the challenges for Safety and Safety Culture?

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Chaewoon [International Policy Department Policy and Standard Division, Korea Institute of Nuclear Safety, 19 Gusung-Dong Yuseong-Ku, 305-338 DAEJEON (Korea, Republic of)

    2008-07-01

    'Statement of Nuclear Safety Policy' declared by the Korean Government elucidates adherence to the principle of 'priority to safety'. The 3. Comprehensive Nuclear Energy Promotion Plan (2007-2011) more specifically addressed the necessity to develop and apply 'safety culture evaluation criteria' and to strengthen safety management of concerned organizations in an autonomous way. Putting these policies as a backdrop, Korean Government has taken diverse safety culture initiatives and has encouraged the relevant organizations to develop safety culture practices of their own accord. Accordingly, KHNP, the operating organization in Korea, developed a 'safety culture performance indicator', which has been used to evaluate safety mind of employees and the evaluation results have been continuously reflected in operational management and training programs. Furthermore, KHNP inserted 'nuclear safety culture subject' into every course of more than two week length, and provided employees with special lectures on safety culture. KINS, the regulatory organization, developed indicators for the safety culture evaluation based on the IAEA Guidelines. Also, KINS has hosted an annual Nuclear Safety Technology Information Meeting to share information between regulatory organizations and industries. Furthermore, KINS provided a nuclear safety culture class to the new employees and they are given a chance to participate in performance of a role-reversal socio-drama. Additionally, KINS developed a safety culture training program, published training materials and conducted a 'Nuclear Safety Culture Basic Course' in October 2007, 4 times of which are planed this year. In conclusion, from Government to relevant organizations, 'nuclear safety culture' concept is embraced as important and has been put into practice on a variety of forms. Specifically, 'education and training' is a starting line and sharing

  16. Using naturalistic driving data to explore the association between traffic safety-related events and crash risk at driver level.

    Science.gov (United States)

    Wu, Kun-Feng; Aguero-Valverde, Jonathan; Jovanis, Paul P

    2014-11-01

    There has been considerable research conducted over the last 40 years using traffic safety-related events to support road safety analyses. Dating back to traffic conflict studies from the 1960s these observational studies of driver behavior have been criticized due to: poor quality data; lack of available and useful exposure measures linked to the observations; the incomparability of self-reported safety-related events; and, the difficulty in assessing culpability for safety-related events. This study seeks to explore the relationships between driver characteristics and traffic safety-related events, and between traffic safety-related events and crash involvement while mitigating some of those limitations. The Virginia Tech Transportation Institute 100-Car Naturalistic Driving Study dataset, in which the participants' vehicles were instrumented with various cameras and sensors during the study period, was used for this study. The study data set includes 90 drivers observed for 12-13 months driving. This study focuses on single vehicle run-off-road safety-related events only, including 14 crashes and 182 safety-related events (30 near crashes, and 152 crash-relevant incidents). Among the findings are: (1) drivers under age 25 are significantly more likely to be involved in safety-related events and crashes; and (2) significantly positive correlations exist between crashes, near crashes, and crash-relevant incidents. Although there is still much to learn about the factors affecting the positive correlation between safety-related events and crashes, a Bayesian multivariate Poisson log-normal model is shown to be useful to quantify the associations between safety-related events and crash risk while controlling for driver characteristics. Copyright © 2014 Elsevier Ltd. All rights reserved.

  17. An observational study of road safety around selected primary schools in Ibadan municipality, Oyo State, Southwestern Nigeria.

    Science.gov (United States)

    Sangowawa, Adesola O; Adebiyi, Akindele O; Faseru, Babalola; Popoola, Olusola J

    2012-01-01

    Child pedestrians have been identified as vulnerable road users. Although walking as a means of transport has health and other benefits, it exposes children to the risk of road traffic injuries. This study was conducted to assess the availability of road safety features around government-owned primary schools in Ibadan municipality. A multistage sampling technique was used to select 46 of the 74 schools in the study area. Some (11) of the selected schools were sited within the same premises and shared a common entrance; thus a total of 35 school premises were eventually observed. Trained research assistants observed the school environment around the selected schools for road safety features such as location of schools, presence of "school", "child crossing" and "speed limit" road signs, and presence of traffic calming devices (road bumps or zebra crossing). Five (14%) of the schools were located on major roads and eight (23%) had road signs indicating that a school was nearby. Seven (20%) had road bumps close to the school, 15 (43%) had a warden who assisted children to cross, and none had a zebra crossing. Five (14%) schools had pedestrian sidewalks. The study revealed that the environment around a number of the observed schools in the municipality compromised the pupils' road safety. The local government, school authorities, parents, and road safety professionals need to institute definite measures to enhance the road safety environment around schools in the municipality.

  18. The School Assessment for Environmental Typology (SAfETy): An Observational Measure of the School Environment.

    Science.gov (United States)

    Bradshaw, Catherine P; Milam, Adam J; Furr-Holden, C Debra M; Johnson, Sarah Lindstrom

    2015-12-01

    School safety is of great concern for prevention researchers, school officials, parents, and students, yet there are a dearth of assessments that have operationalized school safety from an organizational framework using objective tools and measures. Such a tool would be important for deriving unbiased assessments of the school environment, which in turn could be used as an evaluative tool for school violence prevention efforts. The current paper presents a framework for conceptualizing school safety consistent with Crime Prevention through Environmental Design (CPTED) model and social disorganization theory, both of which highlight the importance of context as a driver for adolescents' risk for involvement in substance use and violence. This paper describes the development of a novel observational measure, called the School Assessment for Environmental Typology (SAfETy), which applies CPTED and social disorganizational frameworks to schools to measure eight indicators of school physical and social environment (i.e., disorder, trash, graffiti/vandalism, appearance, illumination, surveillance, ownership, and positive behavioral expectations). Drawing upon data from 58 high schools, we provide preliminary data regarding the validity and reliability of the SAfETy and describe patterns of the school safety indicators. Findings demonstrate the reliability and validity of the SAfETy and are discussed with regard to the prevention of violence in schools.

  19. Prediction of Clinically Relevant Safety Signals of Nephrotoxicity through Plasma Metabolite Profiling

    Directory of Open Access Journals (Sweden)

    W. B. Mattes

    2013-01-01

    Full Text Available Addressing safety concerns such as drug-induced kidney injury (DIKI early in the drug pharmaceutical development process ensures both patient safety and efficient clinical development. We describe a unique adjunct to standard safety assessment wherein the metabolite profile of treated animals is compared with the MetaMap Tox metabolomics database in order to predict the potential for a wide variety of adverse events, including DIKI. To examine this approach, a study of five compounds (phenytoin, cyclosporin A, doxorubicin, captopril, and lisinopril was initiated by the Technology Evaluation Consortium under the auspices of the Drug Safety Executive Council (DSEC. The metabolite profiles for rats treated with these compounds matched established reference patterns in the MetaMap Tox metabolomics database indicative of each compound’s well-described clinical toxicities. For example, the DIKI associated with cyclosporine A and doxorubicin was correctly predicted by metabolite profiling, while no evidence for DIKI was found for phenytoin, consistent with its clinical picture. In some cases the clinical toxicity (hepatotoxicity, not generally seen in animal studies, was detected with MetaMap Tox. Thus metabolite profiling coupled with the MetaMap Tox metabolomics database offers a unique and powerful approach for augmenting safety assessment and avoiding clinical adverse events such as DIKI.

  20. Safety culture and subcontractor network governance in a complex safety critical project

    International Nuclear Information System (INIS)

    Oedewald, Pia; Gotcheva, Nadezhda

    2015-01-01

    In safety critical industries many activities are currently carried out by subcontractor networks. Nevertheless, there are few studies where the core dimensions of resilience would have been studied in safety critical network activities. This paper claims that engineering resilience into a system is largely about steering the development of culture of the system towards better ability to anticipate, monitor, respond and learn. Thus, safety culture literature has relevance in resilience engineering field. This paper analyzes practical and theoretical challenges in applying the concept of safety culture in a complex, dynamic network of subcontractors involved in the construction of a new nuclear power plant in Finland, Olkiluoto 3. The concept of safety culture is in focus since it is widely used in nuclear industry and bridges the scientific and practical interests. This paper approaches subcontractor networks as complex systems. However, the management model of the Olkiluoto 3 project is to a large degree a traditional top-down hierarchy, which creates a mismatch between the management approach and the characteristics of the system to be managed. New insights were drawn from network governance studies. - Highlights: • We studied a relevant topical subject safety culture in nuclear new build project. • We integrated safety science challenges and network governance studies. • We produced practicable insights in managing safety of subcontractor networks

  1. Randomized controlled trials and real-world observational studies in evaluating cardiovascular safety of inhaled bronchodilator therapy in COPD

    Directory of Open Access Journals (Sweden)

    Kardos P

    2016-11-01

    Full Text Available Peter Kardos,1 Sally Worsley,2 Dave Singh,3 Miguel Román-Rodríguez,4 David E Newby,5 Hana Müllerová2 1Group Practice and Respiratory, Allergy and Sleep Unit, Red Cross Maingau Hospital, Frankfurt, Germany; 2GSK, Stockley Park, Middlesex, 3University of Manchester, Medicines Evaluation Unit, University Hospital of South Manchester NHS Foundation Trust, Manchester, UK; 4Primary Care Respiratory Research Unit, Instituto de Investigación Sanitaria de Palma IdisPa, Palma de Mallorca, Spain; 5BHF Centre for Cardiovascular Science, University of Edinburgh, The Queen’s Medical Research Institute, Edinburgh, UK Abstract: Long-acting muscarinic antagonist (LAMA or long-acting β2-agonist (LABA bronchodilators and their combination are recommended for the maintenance treatment of chronic obstructive pulmonary disease (COPD. Although the efficacy of LAMAs and LABAs has been well established through randomized controlled trials (RCTs, questions remain regarding their cardiovascular (CV safety. Furthermore, while the safety of LAMA and LABA monotherapy has been extensively studied, data are lacking for LAMA/LABA combination therapy, and the majority of the studies that have reported on the CV safety of LAMA/LABA combination therapy were not specifically designed to assess this. Evaluation of CV safety for COPD treatments is important because many patients with COPD have underlying CV comorbidities. However, severe CV and other comorbidities are often exclusion criteria for RCTs, contributing to a lack in external validity and generalizability. Real-world observational studies are another important tool to evaluate the effectiveness and safety of COPD therapies in a broader population of patients and can improve upon the external validity limitations of RCTs. We examine what is already known regarding the CV and cerebrovascular safety of LAMA/LABA combination therapy from RCTs and real-world observational studies, and explore the advantages and

  2. Observational Study on Safety of Prehospital BLS CPAP in Dyspnea.

    Science.gov (United States)

    Sahu, Novneet; Matthews, Patrick; Groner, Kathryn; Papas, Mia A; Megargel, Ross

    2017-12-01

    Introduction Continuous positive airway pressure (CPAP) improves outcomes in patients with respiratory distress. Additional benefits are seen with CPAP application in the prehospital setting. Theoretical safety concerns regarding Basic Life Support (BLS) providers using CPAP exist. In Delaware's (USA) two-tiered Emergency Medical Service (EMS) system, BLS often arrives before Advanced Life Support (ALS). Hypothesis This study fills a gap in literature by evaluating the safety of CPAP applied by BLS prior to ALS arrival. This was a retrospective, observational study using Quality Assurance (QA) data collected from October 2009 through December 2012 throughout a state BLS CPAP pilot program; CPAP training was provided to BLS providers prior to participation. Collected data include pulse-oximetry (spO2), respiratory rate (RR), heart rate (HR), skin color, and Glasgow Coma Score (GCS) before and after CPAP application. Pre-CPAP and post-CPAP values were compared using McNemar's and t-tests. Advanced practitioners evaluated whether CPAP was correctly applied and monitored and whether the patient condition was "improved," "unchanged," or "worsened." Seventy-four patients received CPAP by BLS; CPAP was correctly indicated and applied for all 74 patients. Respiratory status and CPAP were appropriately monitored and documented in the majority of cases (98.6%). A total of 89.2% of patients improved and 4.1% worsened; CPAP significantly reduced the proportion of patients with SpO224, and cyanosis (PCPAP (mean difference [MD]=0.17; 95% CI, -0.49 to 0.83; P=.59). The HR decreased from 115.7 (SD=53) to 105.1 (SD=37) after CPAP (MD=-10.9; 95% CI, -3.2 to -18.6; PCPAP (MD=17.8; 95% CI, 14.2-21.5; PCPAP was indicated, to apply it correctly, and to appropriately monitor the status of these patients. The majority of patients who received CPAP by BLS providers had improvement in their clinical status and vital signs. The findings suggest that CPAP can be safely used by BLS providers

  3. Channelized relevance vector machine as a numerical observer for cardiac perfusion defect detection task

    Science.gov (United States)

    Kalayeh, Mahdi M.; Marin, Thibault; Pretorius, P. Hendrik; Wernick, Miles N.; Yang, Yongyi; Brankov, Jovan G.

    2011-03-01

    In this paper, we present a numerical observer for image quality assessment, aiming to predict human observer accuracy in a cardiac perfusion defect detection task for single-photon emission computed tomography (SPECT). In medical imaging, image quality should be assessed by evaluating the human observer accuracy for a specific diagnostic task. This approach is known as task-based assessment. Such evaluations are important for optimizing and testing imaging devices and algorithms. Unfortunately, human observer studies with expert readers are costly and time-demanding. To address this problem, numerical observers have been developed as a surrogate for human readers to predict human diagnostic performance. The channelized Hotelling observer (CHO) with internal noise model has been found to predict human performance well in some situations, but does not always generalize well to unseen data. We have argued in the past that finding a model to predict human observers could be viewed as a machine learning problem. Following this approach, in this paper we propose a channelized relevance vector machine (CRVM) to predict human diagnostic scores in a detection task. We have previously used channelized support vector machines (CSVM) to predict human scores and have shown that this approach offers better and more robust predictions than the classical CHO method. The comparison of the proposed CRVM with our previously introduced CSVM method suggests that CRVM can achieve similar generalization accuracy, while dramatically reducing model complexity and computation time.

  4. KIT safety management. Annual report 2012

    International Nuclear Information System (INIS)

    Frank, Gerhard

    2013-01-01

    The KIT Safety Management Service Unit (KSM) guarantees radiological and conventional technical safety and security of Karlsruhe Institute of Technology and controls the implementation and observation of legal environmental protection requirements. KSM is responsible for - licensing procedures, - industrial safety organization, - control of environmental protection measures, - planning and implementation of emergency preparedness and response, - operation of radiological laboratories and measurement stations, - extensive radiation protection support and the - the execution of security tasks in and for all organizational units of KIT. Moreover, KSM is in charge of wastewater and environmental monitoring for all facilities and nuclear installations all over the KIT campus. KSM is headed by the Safety Commissioner of KIT, who is appointed by the Presidential Committee. Within his scope of procedure for KIT, the Safety Commissioner controls the implementation of and compliance with safety-relevant requirements. The KIT Safety Management is certified according to DIN EN ISO 9001, its industrial safety management is certified by the VBG as ''AMS-Arbeitsschutz mit System'' and, hence, fulfills the requirements of NLF / ISO-OSH 2001. KSM laboratories are accredited according to DIN EN ISO/IEC 17025. To the extent possible, KSM is committed to maintaining competence in radiation protection and to supporting research and teaching activities. The present reports lists the individual tasks of the KIT Safety Management and informs about the results achieved in 2012. Status figures in principle reflect the status at the end of the year 2012. The processes described cover the areas of competence of KSM.

  5. The qualification of electrical components and instrumentations relevant to safety; La qualificazione dei componenti elettrici e di strumentazione rilevanti per la sicurezza

    Energy Technology Data Exchange (ETDEWEB)

    Zambardi, F [ENEA - Direzione Sicurezza Nucleare e Protezione Sanitaria, Divisione Sistemi Elettrici e Strumentazione, Rome (Italy)

    1989-03-15

    Systems and components relevant to safety of nuclear power plants must maintain their functional integrity in order to assure accident prevention and mitigation. Redundancy is utilized against random failures, nevertheless care must be taken to avoid common failures in redundant components. Main sources of degradation and common cause failures consist in the aging effects and in the changes of environmental conditions which occur during the plant life and the postulated accidents. These causes of degradation are expected to be especially significant for instrumentation and electrical equipment, which can have a primary role in safety systems. The qualification is the methodology by which component safety requirements can be met against the above mentioned causes of degradation. In this report the connection between the possible, plant conditions and the resulting degradation effects on components is preliminarily addressed. A general characterization of the qualification is then presented. Basis, methods and peculiar aspects are discussed and the qualification by testing is taken into special account. Technical and organizational aspects related to a plant qualification program are also focused. The report ends with a look to the most significant research and development activities. (author)

  6. Analyzing research trends on drug safety using topic modeling.

    Science.gov (United States)

    Zou, Chen

    2018-04-06

    Published drug safety data has evolved in the past decade due to scientific and technological advances in the relevant research fields. Considering that a vast amount of scientific literature has been published in this area, it is not easy to identify the key information. Topic modeling has emerged as a powerful tool to extract meaningful information from a large volume of unstructured texts. Areas covered: We analyzed the titles and abstracts of 4347 articles in four journals dedicated to drug safety from 2007 to 2016. We applied Latent Dirichlet allocation (LDA) model to extract 50 main topics, and conducted trend analysis to explore the temporal popularity of these topics over years. Expert Opinion/Commentary: We found that 'benefit-risk assessment and communication', 'diabetes' and 'biologic therapy for autoimmune diseases' are the top 3 most published topics. The topics relevant to the use of electronic health records/observational data for safety surveillance are becoming increasingly popular over time. Meanwhile, there is a slight decrease in research on signal detection based on spontaneous reporting, although spontaneous reporting still plays an important role in benefit-risk assessment. The topics related to medical conditions and treatment showed highly dynamic patterns over time.

  7. What is lost when searching only one literature database for articles relevant to injury prevention and safety promotion?

    Science.gov (United States)

    Lawrence, D W

    2008-12-01

    To assess what is lost if only one literature database is searched for articles relevant to injury prevention and safety promotion (IPSP) topics. Serial textword (keyword, free-text) searches using multiple synonym terms for five key IPSP topics (bicycle-related brain injuries, ethanol-impaired driving, house fires, road rage, and suicidal behaviors among adolescents) were conducted in four of the bibliographic databases that are most used by IPSP professionals: EMBASE, MEDLINE, PsycINFO, and Web of Science. Through a systematic procedure, an inventory of articles on each topic in each database was conducted to identify the total unduplicated count of all articles on each topic, the number of articles unique to each database, and the articles available if only one database is searched. No single database included all of the relevant articles on any topic, and the database with the broadest coverage differed by topic. A search of only one literature database will return 16.7-81.5% (median 43.4%) of the available articles on any of five key IPSP topics. Each database contributed unique articles to the total bibliography for each topic. A literature search performed in only one database will, on average, lead to a loss of more than half of the available literature on a topic.

  8. NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security. Issue no. 4, June 2007

    International Nuclear Information System (INIS)

    2007-04-01

    This newsletter contains information on the Centre for Advanced Safety Assessment Tools (CASAT), the new strategy for the recovery of radioactive sources, the Technical Support Organization Conference and a message form the Director of the Division of Nuclear Installation Safety. To improve the efficiency of safety assessment methods, ensure transparency in their validation and application and establish an excellent knowledge base and training programmes, the IAEA's Centre for Advanced Safety Assessment Tools (CASAT) has therefore been formed. The Centre addresses the need for continuous technical support mechanisms for safety assessment methods. It provides support to Member States to enhance their safety assessment capabilities for present and future generations of nuclear systems, with a special focus on countries with a developing nuclear technology and nuclear safety infrastructure. It serves as a consolidated repository of relevant safety analysis knowledge, provides for focused training including advanced analytical simulations, and supports collaboration on safety assessment projects among Member States. The resources provided through CASAT include codes, models, databases, verification and validation information, analytical procedures and guides. The main purpose of the recently established Radioactive Source Technical Coordination Group (RSTCG) is to facilitate the technical coordination of activities of the IAEA related to the control and management of radioactive sources through the development of common approaches in technical matters and to advise the management of the relevant Divisions. It is the task of the RSTCG to provide the programme managers of the participating divisions/sections with a common opinion/advice on technical issues related to the control and management of radioactive sources. The RSTCG members obtain, inter alia from programme managers, information on all relevant project proposals, and share relevant materials in due time to

  9. Safety factor profile dependence of turbulent structure formation in relevant to internal transport barrier relaxation

    International Nuclear Information System (INIS)

    Tokunaga, S.; Yagi, M.; Itoh, S.-I.; Itoh, K.

    2009-01-01

    Full text: It is widely understood that the improved confinement mode with transport barrier is necessary to achieve the self-ignition condition in ITER. The negative magnetic shear, mean ExB flow shear, and zonal flow are considered to play important roles for ITB formation. In our previous study, it is found that the non-linear interaction between the meso-scale modes produces non-local energy transfer to the off-resonant mode in the vicinity of q min surface and brings global relaxation of the temperature profile involving ITB collapse. Experimental studies indicate that a relationship exists between the ITB formation and safety factor q-profile, with a reversed magnetic shear (RS) configuration. Transitional ITB events occur on the low-order rational resonant surface. The ITB shape and location depend on the q-profile and q min position. These observations indicate that the q-profile might play an essential role in determining the turbulent structure. In this study, the effect of safety factor profile on the ion temperature gradient driven drift wave (ITG) turbulence is investigated using a global non-linear simulation code based on the gyro-fluid model. A heat source and toroidal momentum source are introduced. Dependence of safety factor profiles on ITB formation and its stability is examined to clarify the influence of the radial distribution of the rational surfaces and the q min value. It is found that the nonlinearly excited meso-scale mode in the vicinity of q min depends on the value of q min . A detailed analysis of the structure selection rule is in progress. (author)

  10. The Safety Case and Safety Assessment for the Disposal of Radioactive Waste

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-09-15

    This Safety Guide provides guidance and recommendations on meeting the safety requirements in respect of the safety case and supporting safety assessment for the disposal of radioactive waste. The safety case and supporting safety assessment provide the basis for demonstration of safety and for licensing of radioactive waste disposal facilities and assist and guide decisions on siting, design and operations. The safety case is also the main basis on which dialogue with interested parties is conducted and on which confidence in the safety of the disposal facility is developed. This Safety Guide is relevant for operating organizations preparing the safety case as well as for the regulatory body responsible for developing the regulations and regulatory guidance that determine the basis and scope of the safety case. Contents: 1. Introduction; 2. Demonstrating the safety of radioactive waste disposal; 3. Safety principles and safety requirements; 4. The safety case for disposal of radioactive waste; 5. Radiological impact assessment for the period after closure; 6. Specific issues; 7. Documentation and use of the safety case; 8. Regulatory review process.

  11. Industrial safety: its structuring and content

    International Nuclear Information System (INIS)

    Munoz, A.; Rodriguez, J.; Martinez-Val, J.M.

    1999-01-01

    Industrial development has led to an on-going increase in productivity, but the concept of safety has also become highly relevant. In this article, the authors address the structuring and content of industrial safety which involves laying down essential safety requirements, both in manufacturing and processes and in products. (Author)

  12. Observational study of food safety practices in retail deli departments.

    Science.gov (United States)

    Lubran, M B; Pouillot, R; Bohm, S; Calvey, E M; Meng, J; Dennis, S

    2010-10-01

    In order to improve the safety of refrigerated ready-to-eat food products prepared at retail deli departments, a better understanding of current practices in these establishments is needed. Food employees in deli departments at six chain and three independent retail establishments in Maryland and Virginia were observed, using notational analysis, as they prepared deli products for sale. The frequency of contact with objects and deli products before sale, hand washing and glove changing during preparation, and equipment, utensil, and surface cleaning and sanitizing was determined. Compliance with the U.S. Food and Drug Administration's 2005 model Food Code recommendations, which must be adopted by the individual state and local jurisdictions that are responsible for directly regulating retail establishments, was also assessed. Observations indicated there were a large number of actions for which hand washing was recommended at independent and chain stores (273 recommended of 1,098 total actions and 439 recommended of 3,073 total actions, respectively). Moreover, 67% (295 of 439) of the actions for which hand washing was recommended at the chain stores and 86% (235 of 273) of those at the independent stores resulted from employees touching non-food contact surfaces prior to handling ready-to-eat food. Compliance with hand washing recommendations was generally low and varied depending on store type with independent stores exhibiting lower compliance than chain stores (5 instances of compliance for 273 recommended actions and 73 instances of compliance for 439 recommended actions, respectively). Potential risk mitigation measures that may reduce the frequency of hand washing actions needed during ready-to-eat food preparation in retail deli departments are discussed. More research is needed to determine the impact of such measures on food safety.

  13. Automating the Generation of Heterogeneous Aviation Safety Cases

    Science.gov (United States)

    Denney, Ewen W.; Pai, Ganesh J.; Pohl, Josef M.

    2012-01-01

    A safety case is a structured argument, supported by a body of evidence, which provides a convincing and valid justification that a system is acceptably safe for a given application in a given operating environment. This report describes the development of a fragment of a preliminary safety case for the Swift Unmanned Aircraft System. The construction of the safety case fragment consists of two parts: a manually constructed system-level case, and an automatically constructed lower-level case, generated from formal proof of safety-relevant correctness properties. We provide a detailed discussion of the safety considerations for the target system, emphasizing the heterogeneity of sources of safety-relevant information, and use a hazard analysis to derive safety requirements, including formal requirements. We evaluate the safety case using three classes of metrics for measuring degrees of coverage, automation, and understandability. We then present our preliminary conclusions and make suggestions for future work.

  14. Patient Safety, Present and Future

    International Nuclear Information System (INIS)

    Amalberti, R.

    2016-01-01

    Health care tends to oversimplify patient safety concepts. We tend to think about patient safety as a linear dimension that is only associated with the progressive reduction in the number of errors and accidents, with the simple notion that fewer are always better. We consider figures in isolation from the underlying context and prerequisites that drive safety models and the reality of the clinical fields. There is no one ultimate reference model of safety, but many models that can be adapted to fit the various clinical fields requirements and constraints. It is therefore not necessarily a bad result to observe a lower safety figure in a medical domain compared to the figures obtained in nonmedical ultra-safe models. The poor figures may represent the best local safety optimization while coping with the special health care requirements such as a high frequency of unplanned and nonstandard challenges. The paper distinguishes three classes of safety models that fit different field demands: the resilient and adaptive model, the high reliability (HRO) model, and the ultra-safe model. The lecture benchmarks the traits of each model while highlighting the specific dimensions for optimization. The conclusion is that firstly, that since the task requirements dictate the relevance and choice of the model and not the other way around, it is counterproductive to impose a model that is inadequate for the task requirements. Either you move the requirements and change the model, or you keep the constraints, and try to locally optimize the model to the clinical and organizational needs. (author)

  15. Safety case: An international perspective

    International Nuclear Information System (INIS)

    Pescatore, C.; Voinis, S.

    2002-01-01

    In recent years, it has become more and more evident that repository development will involve a number of stages punctuated by interdependent decisions on whether and how to move to the next stage. These decisions require a clear and traceable presentation of technical arguments that will help in giving confidence in the feasibility and safety of the proposed concept. The depth of understanding and technical information available to support decisions will vary from step to step. A safety case is a key item to support the decision to move to the next stage in repository development. Progress is noted, in the past decade, in the performance and safety assessment areas, particularly in the methodologies for repository system analysis. Progress is also observed regarding the understanding of the natural system and its characterisation, treatment of uncertainties, and modelling. Some areas are under active development, e.g. the area of scenario development and analysis. Finally, to increase confidence, rigorous quality assurance procedures need to be implemented, as well as the factoring of the contribution of R and D in underground research laboratories. The paper summarises the lessons learnt within relevant NEA initiatives as they evolved over the course of a decade and now allow a comprehensive view of what constitutes a safety case. (author)

  16. Nuclear safety review for 1984

    International Nuclear Information System (INIS)

    1985-08-01

    This publication is based on the fourth Nuclear Safety Review prepared by the IAEA Secretariat for presentation to the Board of Governors. It discusses relevant international activities in 1984 and the current status of nuclear safety and radiation protection, and looks ahead to anticipated developments

  17. Experiences in assessing safety culture

    International Nuclear Information System (INIS)

    Spitalnik, J.

    2002-01-01

    Based on several Safety Culture self-assessment applications in nuclear organisations, the paper stresses relevant aspects to be considered when programming an assessment of this type. Reasons for assessing Safety Culture, basic principles to take into account, necessary resources, the importance of proper statistical analyses, the feed-back of results, and the setting up of action plans to enhance Safety Culture are discussed. (author)

  18. Monitoring readiness of safety relevant devices in nuclear power plants by means of CRT-colour displays

    International Nuclear Information System (INIS)

    Haubert, R.; Stokke, R.

    1980-01-01

    The development of an information system for monitoring readiness of safety relevant devices is encouraged by the requirements of KTA-rule 3501 (DIN 25434), which states in section 4.9.1.1. 'A display shall be provided for giving a survey of the condition of the components of the reactor protection system and the active engineered safeguards including their energy and auxiliary media supplies'. In the first stage of the development which was reported at the Enlarged Halden Programme Group Meeting in Loen, Norway, 5th-9th June, 1978, only the components of parts of a BWR-protection system were considered and no display was provided. This paper outlines the next step in the development which comprises implementation of the active engineered safeguards into the system and development of a display system based on a colour CRT-screen. A prototype of this computer-based system for monitoring of protection systems has been established, and it is planned to demonstrate this prototype system using the computer equipment at GRS, Garching (orig./HP)

  19. Topical points of community policy concerning nuclear safety relevant to the Internal Market

    International Nuclear Information System (INIS)

    Schroeder, M.

    1991-01-01

    Starting with the Internal Market concept, the lecture describes general and specific expectations directed to the nuclear community from a point of view of nuclear safety, and analyzes those aspects of nuclear safety, EC policy focuses on. There are the following chapters: 1. Selection of sites for nuclear installations, 2. installation and reactor safety, 3. radioactive waste management, 4. decommissioning of nuclear installations, 5. radioactive waste storage, 6. coping with nuclear accidents and other radiological emergency situations. Sophistication of public health and environmental protection within the framework of the EURATOM Treaty is seen in connection with interim and final storage as well as reprocessing of radioactive waste, and with the decommissioning of nuclear facilities on the basis of section 30 ff., and installation and reactor safety on the basis of section 203 EURATOM Treaty. Improving the protection of public health in particular is possible and necessary in order to make the EURATOM community into a proper nuclear community of law. (orig./HSCH) [de

  20. Development of a check sheet for collecting information necessary for occupational safety and health activities and building relevant systems in overseas business places.

    Science.gov (United States)

    Kajiki, Shigeyuki; Kobayashi, Yuichi; Uehara, Masamichi; Nakanishi, Shigemoto; Mori, Koji

    2016-06-07

    This study aimed to develop an information gathering check sheet to efficiently collect information necessary for Japanese companies to build global occupational safety and health management systems in overseas business places. The study group consisted of 2 researchers with occupational physician careers in a foreign-affiliated company in Japan and 3 supervising occupational physicians who were engaged in occupational safety and health activities in overseas business places. After investigating information and sources of information necessary for implementing occupational safety and health activities and building relevant systems, we conducted information acquisition using an information gathering check sheet in the field, by visiting 10 regions in 5 countries (first phase). The accuracy of the information acquired and the appropriateness of the information sources were then verified in study group meetings to improve the information gathering check sheet. Next, the improved information gathering check sheet was used in another setting (3 regions in 1 country) to confirm its efficacy (second phase), and the information gathering check sheet was thereby completed. The information gathering check sheet was composed of 9 major items (basic information on the local business place, safety and health overview, safety and health systems, safety and health staff, planning/implementation/evaluation/improvement, safety and health activities, laws and administrative organs, local medical care systems and public health, and medical support for resident personnel) and 61 medium items. We relied on the following eight information sources: the internet, company (local business place and head office in Japan), embassy/consulate, ISO certification body, university or other educational institutions, and medical institutions (aimed at Japanese people or at local workers). Through multiple study group meetings and a two-phased field survey (13 regions in 6 countries), an information

  1. Evaluating effectiveness and safety toward electronic cigarette among Malaysian vapers: One-month observational study

    Directory of Open Access Journals (Sweden)

    Azizur Rahman

    2016-01-01

    Conclusion: A month follow-up showed a good smoking cessation rate among Malaysian vapers mainly in single users, whereas less number of quitters but the high reduction in tobacco cigarette consumption observed in dual users without any harmful effects. Furthermore, extended period studies are warranted to confirm its long-term safety and effectiveness among different Malaysian population.

  2. Learning from positively deviant wards to improve patient safety: an observational study protocol.

    Science.gov (United States)

    Baxter, Ruth; Taylor, Natalie; Kellar, Ian; Lawton, Rebecca

    2015-12-11

    Positive deviance is an asset-based approach to improvement which has recently been adopted to improve quality and safety within healthcare. The approach assumes that solutions to problems already exist within communities. Certain groups or individuals identify these solutions and succeed despite having the same resources as others. Within healthcare, positive deviance has previously been applied at individual or organisational levels to improve specific clinical outcomes or processes of care. This study explores whether the positive deviance approach can be applied to multidisciplinary ward teams to address the broad issue of patient safety among elderly patients. Preliminary work analysed National Health Service (NHS) Safety Thermometer data from 34 elderly medical wards to identify 5 'positively deviant' and 5 matched 'comparison' wards. Researchers are blinded to ward status. This protocol describes a multimethod, observational study which will (1) assess the concurrent validity of identifying positively deviant elderly medical wards using NHS Safety Thermometer data and (2) generate hypotheses about how positively deviant wards succeed. Patient and staff perceptions of safety will be assessed on each ward using validated surveys. Correlation and ranking analyses will explore whether this survey data aligns with the routinely collected NHS Safety Thermometer data. Staff focus groups and researcher fieldwork diaries will be completed and qualitative thematic content analysis will be used to generate hypotheses about the strategies, behaviours, team cultures and dynamics that facilitate the delivery of safe patient care. The acceptability and sustainability of strategies identified will also be explored. The South East Scotland Research Ethics Committee 01 approved this study (reference: 14/SS/1085) and NHS Permissions were granted from all trusts. Findings will be published in peer-reviewed, scientific journals, and presented at academic conferences. This study

  3. Wind‐gust parametrizations at heights relevant for wind energy: a study based on mast observations

    DEFF Research Database (Denmark)

    Suomi, I.; Vihma, T.; Gryning, Sven-Erik

    2013-01-01

    Wind gusts are traditionally observed and reported at the reference height of 10 m and most gust parametrization methods have been developed only for this height. In many practical applications, e.g. in wind energy, the relevant heights are, however, up to a few hundred metres. In this study, mean...... speed, which is parametrized on the basis of the surface friction velocity, the Obukhov length and height and the boundary‐layer height. The new gust parametrization method outperformed the two older methods: the effects of surface roughness, stability and the height above the surface were well...

  4. Economic consideration of nuclear safety and cost benefit analysis in nuclear safety regulation

    International Nuclear Information System (INIS)

    Choi, Y. S.; Choi, K. S.; Choi, K. W.; Song, I. J.; Park, D. K.

    2001-01-01

    For the optimization of nuclear safety regulation, understanding of economic aspects of it becomes increasingly important together with the technical approach used so far to secure nuclear safety. Relevant economic theories on private and public goods were reviewed to re-illuminate nuclear safety from the economic perspective. The characteristics of nuclear safety as a public good was reviewed and discussed in comparison with the car safety as a private safety good. It was shown that the change of social welfare resulted from the policy change induced can be calculated by the summation of compensating variation(CV) of individuals. It was shown that the value of nuclear safety could be determined in monetary term by this approach. The theoretical background and history of cost benefit analysis of nuclear safety regulation were presented and topics for future study were suggested

  5. Extended storage for radioactive wastes: relevant aspects related to the safety; Almacenamiento prolongado de residuos radiactivos: algunos aspectos de interes a considerar para su seguridad

    Energy Technology Data Exchange (ETDEWEB)

    Castillo, Reinaldo G.; Peralta V, José L.P.; Estevez, Gema G. F., E-mail: gesr@cphr.edu.cu, E-mail: peralta@cphr.edu.cu, E-mail: gema@cphr.edu.cu [Centro de Protección e Higiene de las Radiaciones (CPHR), Agencia de Energía Nuclear y Tecnologías de Avanzada (AENTA), La Habana (Cuba)

    2013-07-01

    The safe management of radioactive waste is an issue of great relevance globally linked to the issue of the peaceful use of nuclear energy. Among the steps in the management of this waste, the safe storage is one of the most important. Given the high costs and uncertainties existing among other aspects of the variants of disposal of radioactive waste, the prolonged storage of these wastes for periods exceeding 50 years is an option that different countries more and more value. One of the fundamental problems to take into account is the safety of the stores, so in this work are evaluated different safety components associated with these facilities through a safety analysis methodology. Elements such as human intrusion, the construction site, the design of the facility, among others are identified as some of the key aspects to take into account when evaluating the safety of these types of facilities. Periods of activities planned for a long-term storage of radioactive waste exceed, in general, the useful life of existing storage facilities. This work identified new challenges to overcome in order to meet the requirements for the achievement of a safe management of radioactive waste without negative impacts on the environment and man.

  6. Non-technical issues in safety assessments for nuclear disposal facilities

    International Nuclear Information System (INIS)

    Kallenbach-Herbert, Beate; Brohmann, Bettina

    2010-09-01

    The paper highlights that a comprehensive approach to safety affords the consideration of technology, organisation, personnel and social environment. In several safety relevant contexts of nuclear waste disposal these fields are closely interrelated. The approach for the consideration of socio-scientific aspects which is sketched in this paper supports the systematic treatment of safety relevant non-technical issues in the safety case or in safety assessments for a disposal project. Furthermore it may foster the dialogue among specialists from the technical, the natural- and the socio-scientific field on questions of disposal safety. In this way it may contribute to a better understanding among the affected scientific disciplines in nuclear waste disposal.

  7. Road Safety Data, Collection, Transfer and Analysis DaCoTa. Workpackage 6, Driver Behaviour Monitoring through Naturalistic Driving: Deliverable 6.3: Report on small scale naturalistic driving pilot.

    NARCIS (Netherlands)

    Pilgerstorfer, M. Runda, K. Brandstätter, C. Christoph, M. Hakkert, S. Ishaq, R. Toledo, T. & Gatscha, M.

    2012-01-01

    WP6 of DaCoTA, Driver Behaviour Monitoring through Naturalistic Driving, aims to develop an implementation plan for a large scale activity that uses Naturalistic Driving (ND) Observations to continuously monitor relevant road safety data within the framework of the European Road Safety Observatory.

  8. Organisational learning and continuous improvement of health and safety in certified manufacturers

    DEFF Research Database (Denmark)

    Granerud, Lise; Rocha, Robson Sø

    2011-01-01

    and raise goals within health and safety on a continuous basis. The article examines how certified occupational and health management systems influence this process to evaluate how far they hinder or support learning. It presents a model with which it is possible to identify and analyse improvement......Certified management systems have increasingly been applied by firms in recent decades and now cover the management of health and safety, principally through the OHSAS 18001 standard. In order to become certified, firms must not only observe the relevant legislation, but also improve performance...... processes. The model is applied to five cases from a qualitative study of Danish manufacturers with certified health and safety management systems. The cases illustrate the wide variation in health and safety management among certified firms. Certification is found to support lower levels of continuous...

  9. System Design and the Safety Basis

    International Nuclear Information System (INIS)

    Ellingson, Darrel

    2008-01-01

    The objective of this paper is to present the Bechtel Jacobs Company, LLC (BJC) Lessons Learned for system design as it relates to safety basis documentation. BJC has had to reconcile incomplete or outdated system description information with current facility safety basis for a number of situations in recent months. This paper has relevance in multiple topical areas including documented safety analysis, decontamination and decommissioning (D and D), safety basis (SB) implementation, safety and design integration, potential inadequacy of the safety analysis (PISA), technical safety requirements (TSR), and unreviewed safety questions. BJC learned that nuclear safety compliance relies on adequate and well documented system design information. A number of PIS As and TSR violations occurred due to inadequate or erroneous system design information. As a corrective action, BJC assessed the occurrences caused by systems design-safety basis interface problems. Safety systems reviewed included the Molten Salt Reactor Experiment (MSRE) Fluorination System, K-1065 fire alarm system, and the K-25 Radiation Criticality Accident Alarm System. The conclusion was that an inadequate knowledge of system design could result in continuous non-compliance issues relating to nuclear safety. This was especially true with older facilities that lacked current as-built drawings coupled with the loss of 'historical knowledge' as personnel retired or moved on in their careers. Walkdown of systems and the updating of drawings are imperative for nuclear safety compliance. System design integration with safety basis has relevance in the Department of Energy (DOE) complex. This paper presents the BJC Lessons Learned in this area. It will be of benefit to DOE contractors that manage and operate an aging population of nuclear facilities

  10. Safety analysis of autonomous excavator functionality

    International Nuclear Information System (INIS)

    Seward, D.; Pace, C.; Morrey, R.; Sommerville, I.

    2000-01-01

    This paper presents an account of carrying out a hazard analysis to define the safety requirements for an autonomous robotic excavator. The work is also relevant to the growing generic class of heavy automated mobile machinery. An overview of the excavator design is provided and the concept of a safety manager is introduced. The safety manager is an autonomous module responsible for all aspects of system operational safety, and is central to the control system's architecture. Each stage of the hazard analysis is described, i.e. system model creation, hazard definition and hazard analysis. Analysis at an early stage of the design process, and on a system that interfaces directly to an unstructured environment, exposes certain issues relevant to the application of current hazard analysis methods. The approach taken in the analysis is described. Finally, it is explained how the results of the hazard analysis have influenced system design, in particular, safety manager specifications. Conclusions are then drawn about the applicability of hazard analysis of requirements in general, and suggestions are made as to how the approach can be taken further

  11. The role of natural analogues in safety assessment and acceptability

    International Nuclear Information System (INIS)

    Papp, Toenis

    1987-01-01

    The safety assessment must evaluate the level of safety for a repository, the confidence that can be placed on the assessment and how well the repository can meet the acceptance criteria of the society. Many of the processes and phenomena that govern the long term performance of a deep geologic repository for radioactive waste also take place in nature. To investigate these natural analogues and try to validate the models on which the safety assessment are based is a main task in the effort to build of confidence in the safety assessments. The assessment of the safety of a repository can, however, not only be based on good models. The possible role of natural analogues or natural evidence in other parts of the safety assessment is discussed. Specially with regard to - the need to demonstrate that all relevant processes have been taken into account, and that the important ones have been validated to an acceptable level for relevant parameters spans, -the definition and analysis of external scenarios for the safety assessment and for the claim that all reasonable scenarios have been addressed, - the public confidence in the long-term relevance of the acceptance criteria. (author)

  12. The quantifying of road safety developments. Paper presented at the International Conference 'Road Safety in Europe', Birmingham, September 9-11, 1996.

    NARCIS (Netherlands)

    Koornstra, M.J.

    1996-01-01

    The evaluation of the effectiveness of road safety policies and measures must be based on quantative information in road safety developments and the relevant variables that influence that development. However, the concept of road safety itself is not well defined theoretically and quantatively. This

  13. Risk-based safety indicators

    International Nuclear Information System (INIS)

    Sedlak, J.

    2001-12-01

    The report is structured as follows: 1. Risk-based safety indicators: Typology of risk-based indicators (RBIs); Tools for defining RBIs; Requirements for the PSA model; Data sources for RBIs; Types of risks monitored; RBIs and operational safety indicators; Feedback from operating experience; PSO model modification for RBIs; RBI categorization; RBI assessment; RBI applications; Suitable RBI applications. 2. Proposal for risk-based indicators: Acquiring information from operational experience; Method of acquiring safety relevance coefficients for the systems from a PSA model; Indicator definitions; On-line indicators. 3. Annex: Application of RBIs worldwide. (P.A.)

  14. The use of probabilistic safety assessments for improving nuclear safety in Europe

    International Nuclear Information System (INIS)

    Birkhofer, A.

    1992-01-01

    The political changes in Europe broadened the scope of international nuclear safety matters considerably. The Western world started to receive reliable and increasingly detailed information on Eastern European nuclear technology and took note of a broad range of technical and administrative problems relevant for nuclear safety in these countries. Reunification made Germany a focus of information exchange on these matters. Here, cooperation with the former German Democratic Republic and with other Eastern European countries as well as safety analyses of Soviet-built nuclear power plants started rather early. Meanwhile, these activities are progressing toward all-European cooperation in the nuclear safety sector. This cooperation includes the use of probabilistic safety assessments (PSAs) addressing applications in both Western and Eastern Europe as well as the further development of this methodology in a converging Europe

  15. Criticality Safety in the Handling of Fissile Material. Specific Safety Guide

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-05-15

    This Safety Guide provides guidance and recommendations on how to meet the relevant requirements for ensuring subcriticality when dealing with fissile material and for planning the response to criticality accidents. The guidance and recommendations are applicable to both regulatory bodies and operating organizations. The objectives of criticality safety are to prevent a self-sustained nuclear chain reaction and to minimize the consequences of this if it were to occur. The Safety Guide makes recommendations on how to ensure subcriticality in systems involving fissile materials during normal operation, anticipated operational occurrences, and, in the case of accident conditions, within design basis accidents, from initial design through commissioning, operation, and decommissioning and disposal.

  16. Structural safety - Is the safety margin measurable

    International Nuclear Information System (INIS)

    Rintamaa, R.

    1992-01-01

    In ensuring the structural safety of the nuclear components one must be aware of the uncertainties related to the material deorientation, loadings and other operational conditions, geometrical dimensions as well as the service environment. Furthermore, the validation of the analysis tools and procedures is of great importance in overall safety assessment of a pressure retaining component. In order to identify and quantify the concerns and risks arising from the uncertainties in the safety related issue intensive research is being carried out all over the world, in particular, on the ageing, plant life extension and management of old nuclear power plants. The presentation includes a general survey of the factors relevant to the assessment of safe and reliable operation of a nuclear component throughout its planned service life. Certain aspects are outlined based on the research work being carried out at the Technical Research Centre of Finland (VTT)(orig.)

  17. Safety Management at PUSPATI TRIGA Reactor (RTP)

    International Nuclear Information System (INIS)

    Ligam, A.S.; Zarina Masood; Ahmad Nabil Abdul Rahim

    2011-01-01

    Adequate safety measures and precautions, which follow relevant safety standards and procedures, should be in place so that personnel safety is assured. Nevertheless, the public, visitor, contractor or anyone who wishes to enter or be in the reactor building should be well informed with the safety measures applied. Furthermore, these same elements of safety are also applied to other irradiation facilities within the premises of Nuclear Malaysia. This paper will describes and explains current safety management system being enforced especially in the TRIGA PUSPATI Reactor (RTP) namely radiation monitoring system, safety equipment, safe work instruction, and interconnected internal and external health, safety and security related departments. (author)

  18. Safety of protein hydrolysates, fractions thereof and

    NARCIS (Netherlands)

    Gertjan Schaafsma

    2009-01-01

    This paper evaluates the safety for humans with regard to consumption of protein hydrolysates and fractions thereof, including bioactive peptides. The available literature on the safety of protein, protein hydrolysates, fractions thereof and free amino acids on relevant food legislation is reviewed

  19. Large Scale Experiments on Spacecraft Fire Safety

    Science.gov (United States)

    Urban, David; Ruff, Gary A.; Minster, Olivier; Fernandez-Pello, A. Carlos; Tien, James S.; Torero, Jose L.; Legros, Guillaume; Eigenbrod, Christian; Smirnov, Nickolay; Fujita, Osamu; hide

    2012-01-01

    Full scale fire testing complemented by computer modelling has provided significant knowhow about the risk, prevention and suppression of fire in terrestrial systems (cars, ships, planes, buildings, mines, and tunnels). In comparison, no such testing has been carried out for manned spacecraft due to the complexity, cost and risk associated with operating a long duration fire safety experiment of a relevant size in microgravity. Therefore, there is currently a gap in knowledge of fire behaviour in spacecraft. The entire body of low-gravity fire research has either been conducted in short duration ground-based microgravity facilities or has been limited to very small fuel samples. Still, the work conducted to date has shown that fire behaviour in low-gravity is very different from that in normal gravity, with differences observed for flammability limits, ignition delay, flame spread behaviour, flame colour and flame structure. As a result, the prediction of the behaviour of fires in reduced gravity is at present not validated. To address this gap in knowledge, a collaborative international project, Spacecraft Fire Safety, has been established with its cornerstone being the development of an experiment (Fire Safety 1) to be conducted on an ISS resupply vehicle, such as the Automated Transfer Vehicle (ATV) or Orbital Cygnus after it leaves the ISS and before it enters the atmosphere. A computer modelling effort will complement the experimental effort. Although the experiment will need to meet rigorous safety requirements to ensure the carrier vehicle does not sustain damage, the absence of a crew removes the need for strict containment of combustion products. This will facilitate the possibility of examining fire behaviour on a scale that is relevant to spacecraft fire safety and will provide unique data for fire model validation. This unprecedented opportunity will expand the understanding of the fundamentals of fire behaviour in spacecraft. The experiment is being

  20. Culturally relevant model program to prevent and reduce agricultural injuries.

    Science.gov (United States)

    Helitzer, D L; Hathorn, G; Benally, J; Ortega, C

    2014-07-01

    Limited research has explored pesticide injury prevention among American Indian farmers. In a five-year agricultural intervention, a university-community partnership, including the University of New Mexico School of Medicine, New Mexico State University, Shiprock Area Cooperative Extension Service, and Navajo Nation communities, used a culturally relevant model to introduce and maintain safe use of integrated pest management techniques. We applied the Diffusion of Innovations theory and community-based approaches to tailor health promotion strategies for our intervention. In a longitudinal study with repeated measures, we trained six "model farmers" to be crop management experts in pesticide safety, application, and control. Subsequently, these model farmers worked with 120 farm families randomized into two groups: intervention (Group 1) and delayed intervention (Group 2). Measurements included a walk-through analysis, test of knowledge and attitudes, and yield analysis. Both groups demonstrated improvements in pesticide storage behaviors after training. Test scores regarding safety practices improved significantly: from 57.3 to 72.4 for Group 1 and from 52.6 to 76.3 for Group 2. Group 1 maintained their knowledge and safety practices after the intervention. Attitudes about pesticides and communication of viewpoints changed across the study years. With pesticides and fertilizer, the number of corn ears increased by 56.3% and yield (kg m(-2)) of alfalfa increased by 41.2%. The study combined traditional farming practices with culturally relevant approaches and behavior change theory to affect knowledge, safety practices, attitudes, communication channels, and crop yield. Storage behaviors, use of pesticides and safety and application equipment, and safety practice knowledge changed significantly, as did attitudes about social networking, social support, and the compatibility and relative advantage of pesticides for farms.

  1. Safety balance: Analysis of safety systems; Bilans de surete: analyse par les organismes de surete

    Energy Technology Data Exchange (ETDEWEB)

    Delage, M; Giroux, C

    1990-12-01

    Safety analysis, and particularly analysis of exploitation of NPPs is constantly affected by EDF and by the safety authorities and their methodologies. Periodic safety reports ensure that important issues are not missed on daily basis, that incidents are identified and that relevant actions are undertaken. French safety analysis method consists of three principal steps. First type of safety balance is analyzed at the normal start-up phase for each unit including the final safety report. This enables analysis of behaviour of units ten years after their licensing. Second type is periodic operational safety analysis performed during a few years. Finally, the third step consists of safety analysis of the oldest units with the aim to improve the safety standards. The three steps of safety analysis are described in this presentation in detail with the aim to present the objectives and principles. Examples of most recent exercises are included in order to illustrate the importance of such analyses.

  2. AEC sets five year nuclear safety research program

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    The research by the government for the establishment of means of judging the adequacy of safety measures incorporated in nuclear facilities, including setting safety standards and collecting documents of general criteria, and the research by the industry on safety measures and the promotion of safety-related technique are stated in the five year program for 1976-80 reported by subcommittees, Atomic Energy Commission (AEC). Four considerations on the research items incorporated in the program are 1) technical programs relating to the safety of nuclear facilities and the necessary criteria, 2) priority of the relevant items decided according to their impact on circumstances, urgency, the defence-indepth concept and so on, 3) consideration of all relevant data and documents collected, and research subjects necessary to quantify safety measurement, and 4) consideration of technological actualization, the capability of each research body, the budget and the time schedule. In addition, seven major themes decided on the basis of these points are 1) reactivity-initiated accident, 2) LOCA, 3) fuel behavior, 4) structural safety, 5) radioactive release, 6) statistical method of safety evaluation, and 7) seismic characteristics. The committee has deliberated the appropriate division of researches between the government and the industry. A set of tables showing the nuclear safety research plan for 1976-80 are attached. (Iwakiri, K.)

  3. Safety of Nuclear Fuel Cycle Facilities. Safety Requirements (Arabic Edition)

    International Nuclear Information System (INIS)

    2015-01-01

    This publication covers the broad scope of requirements for fuel cycle facilities that, in light of the experience and present state of technology, must be satisfied to ensure safety for the lifetime of the facility. Topics of specific relevance include aspects of nuclear fuel generation, storage, reprocessing and disposal

  4. ITER final design report, cost review and safety analysis (FDR) and relevant documents

    International Nuclear Information System (INIS)

    1999-01-01

    This volume contains the fourth major milestone report and documents associated with its acceptance, review and approval. This ITER Final Design Report, Cost Review and Safety Analysis was presented to the ITER Council at its 13th meeting in February 1998 and was approved at its extraordinary meeting on 25 June 1998. The contents include an outline of the ITER objectives, the ITER parameters and design overview as well as operating scenarios and plasma performance. Furthermore, design features, safety and environmental characteristics and schedule and cost estimates are given

  5. Industrial safety in a nuclear decommissioning environment observations and lessons learned

    International Nuclear Information System (INIS)

    Brevig, D.

    2008-01-01

    Decommissioning activities present unusual and unexpected workplace safety challenges that go far beyond the traditional experience of nuclear power plant managers. A blend of state-of-the-art safety program management tools along with new and practical applications are required to ensure high industrial safety performance. The demanding and rigorously applied nuclear safety engineering standards that are accepted as normal and routine in the operation of a nuclear power facility, should transform as an industrial safety standard during the non-operating period of decommissioning. In addition, historical measures of non-nuclear industrial safety injury rates would or should not be acceptable safety behaviors during a nuclear decommissioning project. When complex projects, such as the decommissioning of a nuclear generating facility are undertaken, the workforce brings experience, qualifications, and assumptions to the project. The overall multi-year general schedule is developed, with more schedule details, for example, for the nearest rolling 12-18 months. Methods are established for the selection of contractors to assist in areas that are not normal tasks for the facility workforce, whose normal activity is managing and operating a nuclear generating station. However, it is critical to manage those contractors to the agreed work scope to ensure success is maintained by both parties, e.g. the job gets done, on schedule, on budget, all parties are financially whole when the work is complete, and safely. The purpose of this paper is to provide a perspective of nuclear plant personal safety in the ever changing industrial environment created by the demolition of robust and often radiologically contaminated structures in a nuclear facility decommissioning project. (author)

  6. Industrial safety in a nuclear decommissioning environment observations and lessons learned

    Energy Technology Data Exchange (ETDEWEB)

    Brevig, D. [Independent Consultant, San Clemente (United States)

    2008-07-01

    Decommissioning activities present unusual and unexpected workplace safety challenges that go far beyond the traditional experience of nuclear power plant managers. A blend of state-of-the-art safety program management tools along with new and practical applications are required to ensure high industrial safety performance. The demanding and rigorously applied nuclear safety engineering standards that are accepted as normal and routine in the operation of a nuclear power facility, should transform as an industrial safety standard during the non-operating period of decommissioning. In addition, historical measures of non-nuclear industrial safety injury rates would or should not be acceptable safety behaviors during a nuclear decommissioning project. When complex projects, such as the decommissioning of a nuclear generating facility are undertaken, the workforce brings experience, qualifications, and assumptions to the project. The overall multi-year general schedule is developed, with more schedule details, for example, for the nearest rolling 12-18 months. Methods are established for the selection of contractors to assist in areas that are not normal tasks for the facility workforce, whose normal activity is managing and operating a nuclear generating station. However, it is critical to manage those contractors to the agreed work scope to ensure success is maintained by both parties, e.g. the job gets done, on schedule, on budget, all parties are financially whole when the work is complete, and safely. The purpose of this paper is to provide a perspective of nuclear plant personal safety in the ever changing industrial environment created by the demolition of robust and often radiologically contaminated structures in a nuclear facility decommissioning project. (author)

  7. Nuclear Installation Safety: General Observations and Trends from IAEA Peer Reviews

    International Nuclear Information System (INIS)

    Rzentkowski, G.

    2016-01-01

    The Safety Review Services (SRSs) for nuclear installations address the needs of Member States at all stages of installations’ lifecycle. SRSs are based on the IAEA Safety Standards and are provided on Member States’ request to peer review national regulatory frameworks and safety provisions for nuclear installations. They result in recommendations and suggestions to improve national regulations and operational safety, and serve to exert peer pressure to ensure that that every Member State with nuclear installations recognizes its safety responsibility and the need to comply with the IAEA Safety Standards. This presentation provides an overview of SRSs for Nuclear Installations, including their structure and main subject areas. The presentation also summarizes general findings and trends which clearly demonstrate that there is continuous improvement in regulation of nuclear installations and in safety of their operation. Nevertheless, there is the need to further enhance the efficiency and effectiveness of SRSs through review of the overall governance model and service delivery to better serve the needs of Member States. The presentation points out some areas of improvements which have already been implemented or are being considered for implementation. Just as important, SRSs are conducted by teams of experts from around the world to strengthening international cooperation, ensure diversity and impartiality, and improve the overall quality of the safety review being conducted. The review team members are also provided with the opportunity for mutual learning and sharing good practices among themselves and with the Member State undergoing the review. As a result, SRAs play an important role in a quest to harmonize regulatory requirements and approaches globally. (author)

  8. Modelling and simulation in nuclear safety and the role of experiment

    International Nuclear Information System (INIS)

    Baek, W-P.

    2015-01-01

    'Full text:' Modeling and simulation (M&S) technology is a key element in assuring and enhancing the safety of nuclear installations. The M&S technology has been progressed continuously with the introduction of new designs, improved understanding on relevant physical processes, and the improvement of computing environment. This presentation covers the role, progresses and prospect of M&S technology relevant to nuclear safety. Special attention is given to the effective interaction between M&S and experiment. The expected role of experiment to motivate the advancement of M&S technology is emphasized with some typical examples. Finally, relevant R&D activities of Korea are introduced for thermal-hydraulics and severe accident safety. (author)

  9. Microbiological Food Safety Surveillance in China

    Directory of Open Access Journals (Sweden)

    Xiaoyan Pei

    2015-08-01

    Full Text Available Microbiological food safety surveillance is a system that collects data regarding food contamination by foodborne pathogens, parasites, viruses, and other harmful microbiological factors. It helps to understand the spectrum of food safety, timely detect food safety hazards, and provide relevant data for food safety supervision, risk assessment, and standards-setting. The study discusses the microbiological surveillance of food safety in China, and introduces the policies and history of the national microbiological surveillance system. In addition, the function and duties of different organizations and institutions are provided in this work, as well as the generation and content of the surveillance plan, quality control, database, and achievement of the microbiological surveillance of food safety in China.

  10. Safety analysis of control rod drive computers

    International Nuclear Information System (INIS)

    Ehrenberger, W.; Rauch, G.; Schmeil, U.; Maertz, J.; Mainka, E.U.; Nordland, O.; Gloee, G.

    1985-01-01

    The analysis of the most significant user programmes revealed no errors in these programmes. The evaluation of approximately 82 cumulated years of operation demonstrated that the operating system of the control rod positioning processor has a reliability that is sufficiently good for the tasks this computer has to fulfil. Computers can be used for safety relevant tasks. The experience gained with the control rod positioning processor confirms that computers are not less reliable than conventional instrumentation and control system for comparable tasks. The examination and evaluation of computers for safety relevant tasks can be done with programme analysis or statistical evaluation of the operating experience. Programme analysis is recommended for seldom used and well structured programmes. For programmes with a long, cumulated operating time a statistical evaluation is more advisable. The effort for examination and evaluation is not greater than the corresponding effort for conventional instrumentation and control systems. This project has also revealed that, where it is technologically sensible, process controlling computers or microprocessors can be qualified for safety relevant tasks without undue effort. (orig./HP) [de

  11. Diuron-induced rat urinary bladder carcinogenesis: mode of action and human relevance evaluations using the International Programme on Chemical Safety framework.

    Science.gov (United States)

    Da Rocha, Mitscheli Sanches; Arnold, Lora L; De Oliveira, Maria Luiza Cotrim Sartor; Catalano, Shadia M Ihlaseh; Cardoso, Ana Paula Ferragut; Pontes, Merielen G N; Ferrucio, Bianca; Dodmane, Puttappa R; Cohen, Samuel M; De Camargo, João Lauro V

    2014-05-01

    Diuron, a high volume substituted urea herbicide, induced high incidences of urinary bladder carcinomas and low incidences of kidney pelvis papillomas and carcinomas in rats exposed to high doses (2500 ppm) in a 2-year bioassay. Diuron is registered for both occupational and residential uses and is used worldwide for more than 30 different crops. The proposed rat urothelial mode of action (MOA) for this herbicide consists of metabolic activation to metabolites that are excreted and concentrated in the urine, leading to cytotoxicity, urothelial cell necrosis and exfoliation, regenerative hyperplasia, and eventually tumors. We show evidence for this MOA for diuron using the International Programme on Chemical Safety (IPCS) conceptual framework for evaluating an MOA for chemical carcinogens, and the United States Environmental Protection Agency (USEPA) and IPCS framework for assessing human relevance.

  12. Towards an international classification for patient safety : the conceptual framework

    NARCIS (Netherlands)

    Sherman, H.; Castro, G.; Fletcher, M.; Hatlie, M.; Hibbert, P.; Jakob, R.; Koss, R.; Lewalle, P.; Loeb, J.; Perneger, Th.; Runciman, W.; Thomson, R.; Schaaf, van der T.W.; Virtanen, M.

    2009-01-01

    Global advances in patient safety have been hampered by the lack of a uniform classification of patient safety concepts. This is a significant barrier to developing strategies to reduce risk, performing evidence-based research and evaluating existing healthcare policies relevant to patient safety.

  13. Application of the Pareto principle to identify and address drug-therapy safety issues.

    Science.gov (United States)

    Müller, Fabian; Dormann, Harald; Pfistermeister, Barbara; Sonst, Anja; Patapovas, Andrius; Vogler, Renate; Hartmann, Nina; Plank-Kiegele, Bettina; Kirchner, Melanie; Bürkle, Thomas; Maas, Renke

    2014-06-01

    Adverse drug events (ADE) and medication errors (ME) are common causes of morbidity in patients presenting at emergency departments (ED). Recognition of ADE as being drug related and prevention of ME are key to enhancing pharmacotherapy safety in ED. We assessed the applicability of the Pareto principle (~80 % of effects result from 20 % of causes) to address locally relevant problems of drug therapy. In 752 cases consecutively admitted to the nontraumatic ED of a major regional hospital, ADE, ME, contributing drugs, preventability, and detection rates of ADE by ED staff were investigated. Symptoms, errors, and drugs were sorted by frequency in order to apply the Pareto principle. In total, 242 ADE were observed, and 148 (61.2 %) were assessed as preventable. ADE contributed to 110 inpatient hospitalizations. The ten most frequent symptoms were causally involved in 88 (80.0 %) inpatient hospitalizations. Only 45 (18.6 %) ADE were recognized as drug-related problems until discharge from the ED. A limited set of 33 drugs accounted for 184 (76.0 %) ADE; ME contributed to 57 ADE. Frequency-based listing of ADE, ME, and drugs involved allowed identification of the most relevant problems and development of easily to implement safety measures, such as wall and pocket charts. The Pareto principle provides a method for identifying the locally most relevant ADE, ME, and involved drugs. This permits subsequent development of interventions to increase patient safety in the ED admission process that best suit local needs.

  14. Development of safety related technology and infrastructure for safety assessment

    International Nuclear Information System (INIS)

    Venkat Raj, V.

    1997-01-01

    Development and optimum utilisation of any technology calls for the building up of the necessary infrastructure and backup facilities. This is particularly true for a developing country like India and more so for an advanced technology like nuclear technology. Right from the inception of its nuclear power programme, the Indian approach has been to develop adequate infrastructure in various areas such as design, construction, manufacture, installation, commissioning and safety assessment of nuclear plants. This paper deals with the development of safety related technology and the relevant infrastructure for safety assessment. A number of computer codes for safety assessment have been developed or adapted in the areas of thermal hydraulics, structural dynamics etc. These codes have undergone extensive validation through data generated in the experimental facilities set up in India as well as participation in international standard problem exercises. Side by side with the development of the tools for safety assessment, the development of safety related technology was also given equal importance. Many of the technologies required for the inspection, ageing assessment and estimation of the residual life of various components and equipment, particularly those having a bearing on safety, were developed. This paper highlights, briefly, the work carried out in some of the areas mentioned above. (author)

  15. Cost-Efficient Methods and Processes for Safety Relevant Embedded Systems (CESAR) - An Objective Overview

    Science.gov (United States)

    Jolliffe, Graham

    For developing embedded safety critical systems, industrial companies have to face increasing complexity and variety coupled with increasing regulatory constraints, while costs, performances and time to market are constantly challenged. This has led to a profusion of enablers (new processes, methods and tools), which are neither integrated nor interoperable because they have been developed more or less independently (addressing only a part of the complexity: e.g. Safety) in the absence of internationally recognized open standards. CESAR has been established under ARTEMIS, the European Union's Joint Technology Initiative for research in embedded systems, with the aim to improve this situation and this pa-per will explain what CESAR's objectives are, how they are expected to be achieved and, in particular, how current best practice can ensure that safety engineering requirements can be met.

  16. Work Pressure and Safety Behaviors among Health Workers in Ghana: The Moderating Role of Management Commitment to Safety

    OpenAIRE

    Amponsah-Tawaih, Kwesi; Adu, Michael Appiah

    2016-01-01

    Background: safety and healthy working environment has received numerous research attention over the years. Majority of these researches seem to have been conducted in the construction industry, with little attention in the health sector. Nonetheless, there are couple of studies conducted in Africa that suggest pressure in hospitals. Therefore the aim of the study was to examine how pressure influence safety behavior in the hospitals. With reference to the relevance of safety behavior in prim...

  17. Methods and Processes of Developing the Strengthening the Reporting of Observational Studies in Epidemiology - Veterinary (STROBE-Vet) Statement

    DEFF Research Database (Denmark)

    Sargeant, J. M.; O'Connor, A. M.; Dohoo, I. R.

    2016-01-01

    The reporting of observational studies in veterinary research presents many challenges that often are not adequately addressed in published reporting guidelines. A consensus meeting of experts was organized to develop an extension of the STROBE statement to address observational studies...... and biostatisticians, many of whom hold or have held editorial positions with relevant journals. Prior to the meeting, 19 experts completed a survey about whether they felt any of the 22 items of the STROBE statement should be modified and whether items should be added to address unique issues related to observational...... studies in animal species with health, production, welfare or food safety outcomes. At the meeting, the participants were provided with the survey responses and relevant literature concerning the reporting of veterinary observational studies. During the meeting, each STROBE item was discussed to determine...

  18. Status of the safety certification process of the TRANSRAPID system

    Energy Technology Data Exchange (ETDEWEB)

    Blomerius, J [TUEV Rheinland, Koeln (Germany). Inst. fuer Software, Elektronik, Bahntechnik

    1996-12-31

    Since 20 years TUeV Rheinland is involved in safety certification of maglev technology of the TRANSRAPID type. The process applied is called PASC (Programm Accompanying Safety Certification). The paper reports on safety assessment of relevant subsystems and components (TR07, OCS, guideway components) as well as safety certification in the final program. (HW)

  19. Social but safe? Quality and safety of diabetes-related online social networks.

    Science.gov (United States)

    Weitzman, Elissa R; Cole, Emily; Kaci, Liljana; Mandl, Kenneth D

    2011-05-01

    To foster informed decision-making about health social networking (SN) by patients and clinicians, the authors evaluated the quality/safety of SN sites' policies and practices. Multisite structured observation of diabetes-focused SN sites. Measurements 28 indicators of quality and safety covering: (1) alignment of content with diabetes science and clinical practice recommendations; (2) safety practices for auditing content, supporting transparency and moderation; (3) accessibility of privacy policies and the communication and control of privacy risks; and (4) centralized sharing of member data and member control over sharing. Quality was variable across n=10 sites: 50% were aligned with diabetes science/clinical practice recommendations with gaps in medical disclaimer use (30% have) and specification of relevant glycosylated hemoglobin levels (0% have). Safety was mixed with gaps in external review approaches (20% used audits and association links) and internal review approaches (70% use moderation). Internal safety review offers limited protection: misinformation about a diabetes 'cure' was found on four moderated sites. Of nine sites with advertising, transparency was missing on five; ads for unfounded 'cures' were present on three. Technological safety was poor with almost no use of procedures for secure data storage and transmission; only three sites support member controls over personal information. Privacy policies' poor readability impedes risk communication. Only three sites (30%) demonstrated better practice. Limitations English-language diabetes sites only. The quality/safety of diabetes SN is variable. Observed better practice suggests improvement is feasible. Mechanisms for improvement are recommended that engage key stakeholders to balance autonomy, community ownership, conditions for innovation, and consumer protection.

  20. Safety-relevant assessment concerning the proposals for investigations in proposed locations for stage 3 of the deep geological repositories project; Sicherheitstechnisches Gutachten zum Vorschlag der in Etappe 3 SGT weiter zu untersuchenden geologischen Standortgebiete - Sachplan geologische Tiefenlager, Etappe 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2017-04-15

    This comprehensive report published by the Swiss Federal Nuclear Safety Inspectorate ENSI examines the proposals made by the Swiss National Cooperative for the disposal of Radioactive Waste (NAGRA) concerning proposed locations for deep waste repositories. Important basic considerations to be made when narrowing down the choice of host rock types and the selection of possible locations are discussed. These include, amongst others, safety concepts for the repositories, geological models and technical feasibility of repositories in Opalinus Clay, Brown Dogger layers and marl. The properties of various host rocks are discussed. Methods to be used in choosing at least two possible sites for repositories are considered. Also, the radioactive dosage to be expected at the various sites proposed is discussed. A safety-relevant comparison of the sites is made and an overall assessment is presented. The locations proposed for surface facilities at three proposed locations are discussed. The report is completed with an appendix containing tables and a list of relevant expert reports.

  1. Assessment of Safety Standards for Automotive Electronic Control Systems

    Science.gov (United States)

    2016-06-01

    This report summarizes the results of a study that assessed and compared six industry and government safety standards relevant to the safety and reliability of automotive electronic control systems. These standards include ISO 26262 (Road Vehicles - ...

  2. Regulatory regime and its influence in the nuclear safety

    International Nuclear Information System (INIS)

    Laaksonen, J.

    1999-01-01

    Main elements of nuclear regulatory regime in general is presented. These elements are: national rules and safety regulations, system of nuclear facility licensing, activities of regulatory body. Regulatory body is needed to specify the national safety regulations, review and assess the safety documentation presented to support license application, make inspections to verify fulfilment of safety regulations and license conditions, monitor the quality of work processes of user organization, and to assess whether these processes provide a high safety level, promote high safety culture, promote maintenance and development of national infrastructure relevant to nuclear safety, etc

  3. Safety problems related to the use of MOX assemblies in PWRS

    International Nuclear Information System (INIS)

    Gouffon, A.; Merle, J.P.

    1989-12-01

    Curtailment of the LMFBR program along with the satisfactory performance of the La Hague reprocessing plant, with the consequent availability of large quantities of plutonium, provides Electricite de France (EDF) with the possibility of burning mixed uranium and plutonium oxide fuel (MOX fuel) in the core of certain PWR power plant reactors, hence reducing enriched uranium fuel requirements. Design provision has in fact been made for this possibility on sixteen 900 MWe plant units and is explicitly authorized in the relevant authorization decrees. In this paper, we have restricted our discussion to safety aspects pertaining to utilization of the fuel in the reactor. Generally speaking, the Safety Analysis Department has checked that the provisions made by EDF and/or the scheduled plant modifications enabled reactor unit operating safety to be maintained at the same level as for standard fuel management systems and that, in particular, the recycling of 30% MOX assemblies was compatible with observance, under accident conditions, of the same safety criteria as for all uranium cores

  4. The role of organizational trust in safety climate's influence on organizational outcomes.

    Science.gov (United States)

    Kath, Lisa M; Magley, Vicki J; Marmet, Matthew

    2010-09-01

    Based on elements of social exchange theory and other conceptualizations of trust, a model was developed situating organizational trust as a central component to the relationship that safety climate has with organizational outcomes. Specifically, the model specified that two facets of safety climate--upward safety communication and management attitudes toward safety--would be positively related to organizational trust. Increased levels of trust would then predict increased motivation to engage in safe job-related behaviors, increased job satisfaction, and decreased turnover intentions. Another hypothesis investigated whether job safety relevance would moderate the relationship between safety climate and trust. Online survey research was conducted with 599 employees from 97 work groups across a New England grocery store chain. Hierarchical linear modeling indicated support for trust mediating the relationship between safety climate and organizational outcomes; further, the relationship between safety climate and trust was stronger within work groups where safety was more relevant. 2009 Elsevier Ltd. All rights reserved.

  5. IAEA safety glossary. Terminology used in nuclear safety and radiation protection. 2007 ed

    International Nuclear Information System (INIS)

    2007-01-01

    In developing and establishing standards of safety for protecting people and the environment from harmful effects of ionizing radiation and for the safety of facilities and activities that give rise to radiation risks, clear communication on scientific and technical concepts is essential. The principles, requirements and recommendations that are established and explained in the IAEA's safety standards and elaborated upon in other publications must be clearly expressed. To this end, this Safety Glossary defines and explains technical terms used in IAEA safety standards and other safety related publications, and provides information on their usage. The primary purpose of the Safety Glossary is to harmonize terminology and usage in the IAEA safety standards for protecting people and the environment from harmful effects of ionizing radiation, and in their application. Once definitions of terms have been established, they are, in general, intended to be observed in safety standards and other safety related publications and in the work of the IAEA Department of Nuclear Safety and Security generally. The achievement of consistently high quality in its publications contributes to the authority and credibility of the IAEA, and thus to its influence and effectiveness. High quality in publications and documents is achieved not only by review to ensure that the relevant requirements are met, but also by managing their preparation so as to achieve high quality in their drafting. The Safety Glossary provides guidance primarily for the drafters and reviewers of safety standards, including IAEA technical officers and consultants and bodies for the endorsement of safety standards. The Safety Glossary is also a source of information for users of IAEA safety standards and other safety and security related IAEA publications and for other IAEA staff - notably writers, editors, translators, revisers and interpreters. Users of the Safety Glossary, in particular drafters of national

  6. IAEA safety glossary. Terminology used in nuclear safety and radiation protection. 2007 ed

    International Nuclear Information System (INIS)

    2007-06-01

    In developing and establishing standards of safety for protecting people and the environment from harmful effects of ionizing radiation and for the safety of facilities and activities that give rise to radiation risks, clear communication on scientific and technical concepts is essential. The principles, requirements and recommendations that are established and explained in the IAEA's safety standards and elaborated upon in other publications must be clearly expressed. To this end, this Safety Glossary defines and explains technical terms used in IAEA safety standards and other safety related publications, and provides information on their usage. The primary purpose of the Safety Glossary is to harmonize terminology and usage in the IAEA safety standards for protecting people and the environment from harmful effects of ionizing radiation, and in their application. Once definitions of terms have been established, they are, in general, intended to be observed in safety standards and other safety related publications and in the work of the IAEA Department of Nuclear Safety and Security generally. The achievement of consistently high quality in its publications contributes to the authority and credibility of the IAEA, and thus to its influence and effectiveness. High quality in publications and documents is achieved not only by review to ensure that the relevant requirements are met, but also by managing their preparation so as to achieve high quality in their drafting. The Safety Glossary provides guidance primarily for the drafters and reviewers of safety standards, including IAEA technical officers and consultants and bodies for the endorsement of safety standards. The Safety Glossary is also a source of information for users of IAEA safety standards and other safety and security related IAEA publications and for other IAEA staff - notably writers, editors, translators, revisers and interpreters. Users of the Safety Glossary, in particular drafters of national

  7. IAEA safety glossary. Terminology used in nuclear safety and radiation protection. 2007 ed

    International Nuclear Information System (INIS)

    2007-01-01

    In developing and establishing standards of safety for protecting people and the environment from harmful effects of ionizing radiation and for the safety of facilities and activities that give rise to radiation risks, clear communication on scientific and technical concepts is essential. The principles, requirements and recommendations that are established and explained in the IAA's safety standards and elaborated upon in other publications must be clearly expressed. To this end, this Safety Glossary defines and explains technical terms used in IAEA safety standards and other safety related publications, and provides information on their usage. The primary purpose of the Safety Glossary is to harmonize terminology and usage in the IAEA safety standards for protecting people and the environment from harmful effects of ionizing radiation, and in their application. Once definitions of terms have been established, they are, in general, intended to be observed in safety standards and other safety related publications and in the work of the IAEA Department of Nuclear Safety and Security generally. The achievement of consistently high quality in its publications contributes to the authority and credibility of the IAEA, and thus to its influence and effectiveness. High quality in publications and documents is achieved not only by review to ensure that the relevant requirements are met, but also by managing their preparation so as to achieve high quality in their drafting. The Safety Glossary provides guidance primarily for the drafters and reviewers of safety standards, including IAEA technical officers and consultants and bodies for the endorsement of safety standards. The Safety Glossary is also a source of information for users of IAEA safety standards and other safety and security related IAEA publications and for other IAEA staff - notably writers, editors, translators, revisers and interpreters. Users of the Safety Glossary, in particular drafters of national

  8. Leadership and Safety Culture: Leadership for Safety

    International Nuclear Information System (INIS)

    Fischer, E.

    2016-01-01

    Following the challenge to operate Nuclear Power Plants towards operational excellence, a highly skilled and motivated organization is needed. Therefore, leadership is a valuable success factor. On the other hand a well-engineered safety orientated design of NPP’s is necessary. Once built, an NPP constantly requires maintenance, ageing management and lifetime modifications. E.ON tries to keep the nuclear units as close as possible to the state of the art of science and technology. Not at least a requirement followed by our German regulation. As a consequence of this we are continuously challenged to improve our units and the working processes using national and international operational experiences too. A lot of modifications are driven by our self and by regulators. That why these institutions — authorities and independent examiners—contribute significantly to the safety success. Not that it is easy all the day. The relationship between the regulatory body, examiners and the utilities should be challenging but also cooperative and trustful within a permanent dialog. To reach the common goal of highest standards regarding nuclear safety all parties have to secure a living safety culture. Without this attitude there is a higher risk that safety relevant aspects may stay undetected and room for improvement is not used. Nuclear operators should always be sensitized and follow each single deviation. Leaders in an NPP-organization are challenged to create a safety-, working-, and performance culture based on clear common values and behaviours, repeated and lived along all of our days to create a least a strong identity in the staffs mind to the value of safety, common culture and overall performance. (author)

  9. The biological basis of plutonium safety standards

    International Nuclear Information System (INIS)

    Mole, R.H.

    1976-01-01

    Since no radiation injury or cancer in man can, as yet, be directly attributed to Pu, all safety standards for Pu must be determined by reference to other safety standards, development of which is discussed. A system of safety standards must be based on links with real damage, such as the requirement for 226 Ra in bone. The type of biological information required for making standards realistic is considered in relation to Pu and Ra in bone. Also considered are the possible effects of Pu in soft tissue such as bone marrow. Not only dose, but also the number of cells exposed to the dose are important biologically and cellular aspects are examined. Since there is no positive evidence of Pu toxicity relevant information on other α emitters must be examined. The observed effectiveness of Ra, daughters of 222 Ra and 232 Th in causing mutations and cancer, is surveyed. Reference is made to the necessity of improving the ICRP system, currently based on the critical organ concept, by recognising the need for summation of risks in other organs where exposure to Pu is concerned. Improved biological understanding particularly that of hereditary damage, in recent years leads to less pessimistic thinking on the effects of ionizing radiations. The immediate need appears to be for consistency in safety standards. (U.K.)

  10. Global Nuclear Safety and Security Network

    International Nuclear Information System (INIS)

    Guo Lingquan

    2013-01-01

    The objectives of the Regulatory Network are: - to contribute to the effectiveness of nuclear regulatory systems; - to contribute to continuous enhancements, and - to achieve and promote radiation and nuclear safety and security by: • Enhancing the effectiveness and efficiency of international cooperation in the regulation of nuclear and radiation safety of facilities and activities; • Enabling adequate access by regulators to relevant safety and security information; • Promoting dissemination of information on safety and security issues as well as information of good practices for addressing and resolving these issues; • Enabling synergies among different web based networks with a view to strengthening and enhancing the global nuclear safety framework and serving the specific needs of regulators and international organizations; • Providing additional information to the public on international regulatory cooperation in safety and security matters

  11. Definition of the OPERA safety case for radioactive waste disposal in the Netherlands

    International Nuclear Information System (INIS)

    Hart, Jaap; Wildenborg, Ton; Davis, Paul; Becker, Dirk-Alexander; Verhoef, Ewoud

    2014-01-01

    This paper first gives a short introduction on OPERA, the current Dutch five-year research programme on disposal of radioactive waste. It then zooms in on OPERA WP (Work Package) 2 Safety Case - the OSCAR project, and presents (preliminary) results on the structure of the OPERA safety case, the subject of safety statements, and the OPERA safety assessment methodology. The structure of the initial long-term, post-closure safety case for a disposal facility for radioactive waste in Boom Clay in the Netherlands is being developed in the OSCAR project. Hereto a selection of relevant national and international efforts concerning the set-up of a safety case for geological disposal of radioactive waste (safety case structure, safety assessment methodology, FEP database) has been reviewed considering the objectives and outlines of the OPERA programme described in the OPERA research plan. Not surprisingly, it turned out that the guidelines and databases of the IAEA and NEA developed by the international community pretty well covered all aspects of nationally developed safety cases. Although in OPERA only 'initial and conditional' safety cases (for disposal in low permeable clay and rock salt) will be developed, the programme objective is detailing a first road-map for the long-term research on geological disposal of radioactive waste in the Netherlands. The safety case being developed will serve as a basis for the further development of the subsequent stages of the Dutch radioactive waste disposal programme. The focus of OSCAR is, therefore, to develop and propose a 'future proof' structure for the safety case, drawing on the NEA and IAEA/PRISM methodologies. The OPERA safety case structure being developed will encompass all relevant aspects, or components, of a modern safety case and will link the different components in a practical and transparent way. It will assist in steering the flow of information generated within the different OPERA and as such provide a structured

  12. [Organisational responsibility versus individual responsibility: safety culture? About the relationship between patient safety and medical malpractice law].

    Science.gov (United States)

    Hart, Dieter

    2009-01-01

    The contribution is concerned with the correlations between risk information, patient safety, responsibility and liability, in particular in terms of liability law. These correlations have an impact on safety culture in healthcare, which can be evaluated positively if--in addition to good quality of medical care--as many sources of error as possible can be identified, analysed, and minimised or eliminated by corresponding measures (safety or risk management). Liability influences the conduct of individuals and enterprises; safety is (probably) also a function of liability; this should also apply to safety culture. The standard of safety culture does not only depend on individual liability for damages, but first of all on strict enterprise liability (system responsibility) and its preventive effects. Patient safety through quality and risk management is therefore also an organisational programme of considerable relevance in terms of liability law.

  13. Permanent Commission for Health and Safety

    CERN Multimedia

    Association du personnel

    2007-01-01

    The mandate of the Staff Association's permanent commission for Health and Safety is to examine all aspects of health and safety related to the working environment at CERN. In no way does it wish to be a substitute for the official bodies that are responsible for these matters. The Commission's aim is to formulate remarks on and make proposals about these questions to the relevant bodies and the CERN Management. Its main focus is the safety of the CERN staff but it is also concerned with the safety of the installations and of the CERN environment. The Commission reports to the Staff Council and the Executive Committee of the Staff Association.

  14. RF radiation safety handbook

    International Nuclear Information System (INIS)

    Kitchen, Ronald.

    1993-01-01

    Radio frequency radiation can be dangerous in a number of ways. Hazards include electromagnetic compatibility and interference, electro-explosive vapours and devices, and direct effects on the human body. This book is a general introduction to the sources and nature of RF radiation. It describes the ways in which our current knowledge, based on relevant safety standards, can be used to safeguard people from any harmful effects of RF radiation. The book is designed for people responsible for, or concerned with, safety. This target audience will primarily be radio engineers, but includes those skilled in other disciplines including medicine, chemistry or mechanical engineering. The book covers the problems of RF safety management, including the use of measuring instruments and methods, and a review of current safety standards. The implications for RF design engineers are also examined. (Author)

  15. Long term safety requirements and safety indicators for the assessment of underground radioactive waste repositories

    International Nuclear Information System (INIS)

    Vovk, Ivan

    1998-01-01

    This presentation defines: waste disposal, safety issues, risk estimation; describes the integrated waste disposal process including quality assurance program. Related to actinides inventory it shows the main results of calculated activity obtained by deterministic estimation. It includes the Radioactive Waste Safety Standards and requirements; features related to site, design and waste package characteristics, as technical long term safety criteria for radioactive waste disposal facilities. Fundamental concern regarding the safety of radioactive waste disposal systems is their radiological impact on human beings and the environment. Safety requirements and criteria for judging the level of safety of such systems have been developed and there is a consensus among the international community on their basis within the well-established system of radiological protection. So far, however, little experience has been gained in applying long term safety criteria to actual disposal systems; consequently, there is an international debate on the most appropriate nature and form of the criteria to be used, taking into account the uncertainties involved. Emerging from the debate is the increasing conviction that the combined use of a variety of indicators would be advantageous in addressing the issue of reasonable assurance in the different time frames involved and in supporting the safety case for any particular repository concept. Indicators including risk, dose, radionuclide concentration, transit time, toxicity indices, fluxes at different points within the system, and barrier performance have all been identified as potentially relevant. Dose and risk are the indicators generally seen as most fundamental, as they seek directly to describe the radiological impact of a disposal system, and these are the ones that have been incorporated into most national standards to date. There are, however, certain problems in applying them. Application of a variety of different indicators

  16. KIT safety management. Annual report 2012; KIT-Sicherheitsmanagement. Jahresbericht 2012

    Energy Technology Data Exchange (ETDEWEB)

    Frank, Gerhard (ed.)

    2013-07-01

    The KIT Safety Management Service Unit (KSM) guarantees radiological and conventional technical safety and security of Karlsruhe Institute of Technology and controls the implementation and observation of legal environmental protection requirements. KSM is responsible for - licensing procedures, - industrial safety organization, - control of environmental protection measures, - planning and implementation of emergency preparedness and response, - operation of radiological laboratories and measurement stations, - extensive radiation protection support and the - the execution of security tasks in and for all organizational units of KIT. Moreover, KSM is in charge of wastewater and environmental monitoring for all facilities and nuclear installations all over the KIT campus. KSM is headed by the Safety Commissioner of KIT, who is appointed by the Presidential Committee. Within his scope of procedure for KIT, the Safety Commissioner controls the implementation of and compliance with safety-relevant requirements. The KIT Safety Management is certified according to DIN EN ISO 9001, its industrial safety management is certified by the VBG as ''AMS-Arbeitsschutz mit System'' and, hence, fulfills the requirements of NLF / ISO-OSH 2001. KSM laboratories are accredited according to DIN EN ISO/IEC 17025. To the extent possible, KSM is committed to maintaining competence in radiation protection and to supporting research and teaching activities. The present reports lists the individual tasks of the KIT Safety Management and informs about the results achieved in 2012. Status figures in principle reflect the status at the end of the year 2012. The processes described cover the areas of competence of KSM.

  17. CANDU reactors, their regulation in Canada, and the identification of relevant NRC safety issues

    International Nuclear Information System (INIS)

    Charak, I.; Kier, P.H.

    1995-04-01

    Atomic Energy of Canada, Limited (AECL) and its subsidiary in the US, are considering submitting the CANDU 3 design for standard design certification under 10 CFR Part 52. CANDU reactors are pressurized heavy water power reactors. They have some substantially different safety responses and safety systems than the LWRs that the commercial power reactor licensing regulations of the US Nuclear Regulatory Commission (NRC) have been developed to deal with. In this report, the authors discuss the basic design characteristics of CANDU reactors, specifically of the CANDU 3 where possible, and some safety-related consequences of these characteristics. The authors also discuss the Canadian regulatory provisions, and the CANDU safety systems that have evolved to satisfy the Canadian regulatory requirements as of December 1992. Finally, the authors identify NRC regulations, mainly in 10 CFR Parts 50 and 100, with issues for CANDU 3 reactor designs. In all, eleven such regulatory issues are identified. They are: (1) the ATWS rule (section 50.62); (2) station blackout (section 50.63); (3) conformance with Standard Review Plan (SRP); (4) appropriateness of the source term (section 50.34(f) and section 100.11); (5) applicability of reactor coolant pressure boundary (RCPB) requirements (section 50.55a, etc); (6) ECCS acceptance criteria (section 50.46)(b); (7) combustible gas control (section 50.44, etc); (8) power coefficient of reactivity (GDC 11); (9) seismic design (Part 100); (10) environmental impacts of the fuel cycle (section 51.51); and (11) (standards section 50.55a)

  18. The consideration of ecological safety in judicial practice-also on the ecological safety legislation

    Institute of Scientific and Technical Information of China (English)

    L(U) Zhongmei

    2006-01-01

    Ecological safety has been one of the hot issues of environmental law in recent years.The maintenance of ecological safety has become one of the legislative principles,as exemplified by the revision of the Law of Sand Prevention and Sand.Management and the Law against Solid Waste Environmental Pollution,and the relevant rules that will be established.However actual cases will still happen,whether the legislators have made the statutory law or not.While scholars and legislators are debating,the judges have to handle cases and render judgments.Through the analysis of a case,this article will discuss the feasibility for judges to make ecological safety considerations in the judicial process by applying the principle of good faith and will also discuss the legislative issues related to ecological safety.

  19. Mining Behavior Based Safety Data to Predict Safety Performance

    Energy Technology Data Exchange (ETDEWEB)

    Jeffrey C. Joe

    2010-06-01

    The Idaho National Laboratory (INL) operates a behavior based safety program called Safety Observations Achieve Results (SOAR). This peer-to-peer observation program encourages employees to perform in-field observations of each other's work practices and habits (i.e., behaviors). The underlying premise of conducting these observations is that more serious accidents are prevented from occurring because lower level “at risk” behaviors are identified and corrected before they can propagate into culturally accepted “unsafe” behaviors that result in injuries or fatalities. Although the approach increases employee involvement in safety, the premise of the program has not been subject to sufficient empirical evaluation. The INL now has a significant amount of SOAR data on these lower level “at risk” behaviors. This paper describes the use of data mining techniques to analyze these data to determine whether they can predict if and when a more serious accident will occur.

  20. You can't improve what you don't measure: Safety climate measures available in the German-speaking countries to support safety culture development in healthcare.

    Science.gov (United States)

    Manser, Tanja; Brösterhaus, Mareen; Hammer, Antje

    2016-01-01

    Safety climate measurement is a key input into safety culture development. The aim of this review is to provide an overview of the safety climate measures that have been evaluated for their psychometric properties in a German-speaking country and to make recommendations on how to use them in quality and patient safety improvement. A systematic search strategy was implemented to obtain relevant articles. PubMed and Web of Science databases were searched, and 128 abstracts were identified. After application of limits, 33 full texts were retrieved for subsequent evaluation. Studies were included on the basis of predetermined inclusion criteria and independent assessment by two reviewers. Publications were reviewed concerning healthcare setting, target group, safety culture dimensions covered and results of their psychometric evaluation. This review identified 11 instruments for safety climate assessment in different healthcare settings (i. e. hospitals, nursing homes, primary care, dental care and community pharmacy) for which acceptable to good internal consistency was reported. We observed wide variability concerning the number of dimensions (1 to 14; in some cases including outcome dimensions) and items (9 to 128) that the instruments were comprised of. Nevertheless, consistency with regard to the thematic areas covered was rather high. While there is clear evidence that we can assess safety climate in healthcare, the application of safety climate measures by quality and patient safety practitioners has so far been rather limited. This review bridges this gap between research and improvement practice by highlighting the central role of safety climate assessment in a mixed methods approach to inform safety culture development. Copyright © 2016. Published by Elsevier GmbH.

  1. Safety relevant aspects of the long-term intermediate storage of spent fuel elements and vitrified high-level radioactive wastes; Sicherheitstechnische Aspekte der langfristigen Zwischenlagerung von bestrahlten Brennelementen und verglastem HAW

    Energy Technology Data Exchange (ETDEWEB)

    Ellinger, A.; Geupel, S.; Gewehr, K.; Gmal, B.; Hannstein, V.; Hummelsheim, K.; Kilger, R.; Wagner, M. [Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH (GRS), Koeln (Germany); Schmidt, G.; Spieth-Achtnich, A. [Oeko-Institut e.V. - Institut fuer angewandte Oekolgie (Germany)

    2010-04-15

    The currently in Germany pursued concept for management of spent fuel from nuclear power plants provides intermediate dry cask storage at the NPP sites until direct disposal in a deep geologic repository. In addition the earlier commissioned centralized dry storage facilities are being used for storage of high level radioactive waste returned from foreign reprocessing of German spent fuel performed so far. The dry interim storage facilities are licensed for 40 years of operation time. According to the German regulations a full scope periodic safety review is not required so far, neither practical experience on dry storage for this period of time is available. With regard to this background the report at hand is dealing with long term effects, which may affect safety of the interim storage during the 40 years period or beyond if appropriate, and with the question, whether additional analyses or monitoring measures may be required. Therefore relevant publications have been evaluated, calculations have been performed as well as a systematic screening with regard to loads and possible ageing effects has been applied to structures and components important for safety of the storage, in order to identify relevant long term effects, which may not have been considered sufficiently so far and to provide proposals for an improved ageing management. The report firstly provides an overview on the current state of technology describing shortly the national and international practice and experience. In the following chapters safety aspects of interim storage with regard to time dependent effects and variations are being analyzed and discussed. Among this not only technical aspects like the long term behavior of fuel elements, canisters and storage systems are addressed, but also operational long term aspects regarding personnel planning, know how conservation, documentation and quality management are taken into account. A separate chapter is dedicated to developing and describing

  2. In situ observations of oxide fracture on austenitic stainless steels relevant to IASCC

    International Nuclear Information System (INIS)

    Duff, J.; Burke, M.G.; Scenini, F.

    2015-01-01

    Stress Corrosion Cracking (SCC) and Irradiation-Assisted Stress Corrosion Cracking (IASCC) are important failure modes in the nuclear industry, yet the exact mechanism(s) responsible for these complex failure phenomena are not fully understood. In particular, considerable attention is being focused on SCC and IASCC initiation and the behaviour of the oxidised metal surface during straining in a relevant environment. Experimental observations and data for oxide fracture at the grain boundary are limited, but are also required for the development of crack growth models. In this work, the role of strain localization on surface oxide fracture has been examined via: 1) in situ straining experiments using a state-of-the-art imaging autoclave; and 2) ex situ studies using pre-oxidised samples in a FEG-SEM with a micro-tensile stage. The work was conducted using three materials: 1) a non-irradiated archive Type 316 Stainless Steel, 2) a 1 dpa proton-irradiated Type 316 Stainless Steel, and 3) a model alloy designed to simulate the grain boundary composition resulting from radiation induced segregation. The observations were performed on samples pre-oxidized at 320 C. degrees in high purity, water containing 30 cm 3 /kg of dissolved H 2 and 2 ppm Li additions. The samples were strained in tension and the surface deformation measured via Digital Image Correlation. This technique provided quantitative data regarding the intergranular strains associated with oxide fracture. Oxide fracture and strain development were also related to the local irradiation-induced microstructure and grain boundary character. The results from this work contribute to the mechanistic information on the role of strain localization and composition on the incubation stages of IASCC. (authors)

  3. Understanding the role of sleep quality and sleep duration in commercial driving safety.

    Science.gov (United States)

    Lemke, Michael K; Apostolopoulos, Yorghos; Hege, Adam; Sönmez, Sevil; Wideman, Laurie

    2016-12-01

    Long-haul truck drivers in the United States suffer disproportionately high injury rates. Sleep is a critical factor in these outcomes, contributing to fatigue and degrading multiple aspects of safety-relevant performance. Both sleep duration and sleep quality are often compromised among truck drivers; however, much of the efforts to combat fatigue focus on sleep duration rather than sleep quality. Thus, the current study has two objectives: (1) to determine the degree to which sleep impacts safety-relevant performance among long-haul truck drivers; and (2) to evaluate workday and non-workday sleep quality and duration as predictors of drivers' safety-relevant performance. A non-experimental, descriptive, cross-sectional design was employed to collect survey and biometric data from 260 long-haul truck drivers. The Trucker Sleep Disorders Survey was developed to assess sleep duration and quality, the impact of sleep on job performance and accident risk, and other relevant work organization characteristics. Descriptive statistics assessed work organization variables, sleep duration and quality, and frequency of engaging in safety-relevant performance while sleepy. Linear regression analyses were conducted to evaluate relationships between sleep duration, sleep quality, and work organization variables with safety composite variables. Drivers reported long work hours, with over 70% of drivers working more than 11h daily. Drivers also reported a large number of miles driven per week, with an average of 2,812.61 miles per week, and frequent violations of hours-of-service rules, with 43.8% of drivers "sometimes to always" violating the "14-h rule." Sleep duration was longer, and sleep quality was better, on non-workdays compared on workdays. Drivers frequently operated motor vehicles while sleepy, and sleepiness impacted several aspects of safety-relevant performance. Sleep quality was better associated with driving while sleepy and with job performance and concentration

  4. Current R and D status on material motion and interactions relevant to core disruptive accidents

    Energy Technology Data Exchange (ETDEWEB)

    Kondo, Satoru [Safety Engineering Division, O-arai Engineering Center, Power Reactor and Nuclear Fuel Development Corporation, O-arai, Ibaraki (Japan)

    1994-07-01

    In this paper, the current status of research and development activities are briefly reviewed on evaluation of material-coolant interactions and material movement and relocation relevant to the safety of liquid-metal fast reactors. Since the status of European activities are well summarized in other papers submitted to the present meeting, the activities in Japan and the United States are highlighted in this paper. The review includes: out-of-pile experiments, in-pile experiments and relevant computer code development. It is emphasized that improved understanding on material motion has contributed to establishing more realistic and rational safety evaluation methods, where various mitigation mechanisms are inherently effective. (author)

  5. Editorial safety science special issue road safety management.

    NARCIS (Netherlands)

    Wegman, F.C.M. & Hagezieker, M.P.

    2014-01-01

    The articles presented in this Special Issue on Road Safety Management represent an illustration of the growing interest in policy-related research in the area of road safety. The complex nature of this type of research combined with the observation that scientific journals pay limited attention to

  6. The surgical safety checklist and patient outcomes after surgery: a prospective observational cohort study, systematic review and meta-analysis

    NARCIS (Netherlands)

    Abbott, T. E. F.; Ahmad, T.; Phull, M. K.; Fowler, A. J.; Hewson, R.; Biccard, B. M.; Chew, M. S.; Gillies, M.; Pearse, R. M.; Pearse, Rupert M.; Beattie, Scott; Clavien, Pierre-Alain; Demartines, Nicolas; Fleisher, Lee A.; Grocott, Mike; Haddow, James; Hoeft, Andreas; Holt, Peter; Moreno, Rui; Pritchard, Naomi; Rhodes, Andrew; Wijeysundera, Duminda; Wilson, Matt; Ahmed, Tahania; Everingham, Kirsty; Hewson, Russell; Januszewska, Marta; Phull, Mandeep-Kaur; Halliwell, Richard; Shulman, Mark; Myles, Paul; Schmid, Werner; Hiesmayr, Michael; Wouters, Patrick; de Hert, Stefan; Lobo, Suzana; Fang, Xiangming; Rasmussen, Lars; Futier, Emmanuel; Biais, Matthieu; Venara, Aurélien; Slim, Karem; Sander, Michael; Koulenti, Despoina; Arvaniti, Kostoula; Chan, Mathew; Kulkarni, Atul; Chandra, Susilo; Tantri, Aida; Geddoa, Emad; Abbas, Muntadhar; Della Rocca, Giorgio; Sivasakthi, Datin; Mansor, Marzida; Luna, Pastor; Bouwman, Arthur; Buhre, Wolfgang; Beavis, Vanessa; Campbell, Douglas; Short, Tim; Osinaike, Tunde; Matos, Ricardo; Grigoras, Ioana; Kirov, Mikhail; Protsenko, Denis; Biccard, Bruce; Aldecoa, Cesar; Chew, Michelle; Hofer, Christoph; Hubner, Martin; Ditai, James; Szakmany, Tamas; Fleisher, Lee; Ferguson, Marissa; MacMahon, Michael; Cherian, Ritchie; Currow, Helen; Kanathiban, Kathirgamanathan; Gillespie, David; Pathmanathan, Edward; Phillips, Katherine; Reynolds, Jenifer; Rowley, Joanne; Douglas, Jeanene; Kerridge, Ross; Garg, Sameer; Bennett, Michael; Jain, Megha; Alcock, David; Terblanche, Nico; Cotter, Rochelle; Leslie, Kate; Stewart, Marcelle; Zingerle, Nicolette; Clyde, Antony; Hambidge, Oliver; Rehak, Adam; Cotterell, Sharon; Huynh, Wilson Binh Quan; McCulloch, Timothy; Ben-Menachem, Erez; Egan, Thomas; Cope, Jennifer; Fellinger, Paul; Haisjackl, Markus; Haselberger, Simone; Holaubek, Caroline; Lichtenegger, Paul; Scherz, Florian; Hoffer, Franz; Cakova, Veronika; Eichwalder, Andreas; Fischbach, Norbert; Klug, Reinhold; Schneider, Elisabeth; Vesely, Martin; Wickenhauser, Reinhart; Grubmueller, Karl Gernot; Leitgeb, Marion; Lang, Friedrich; Toro, Nancy; Bauer, Marlene; Laengle, Friedrich; Haberl, Claudia; Mayrhofer, Thomas; Trybus, Christoph; Buerkle, Christian; Forstner, Karin; Germann, Reinhard; Rinoesl, Harald; Schindler, Elke; Trampitsch, Ernst; Bogner, Gerhard; Dankl, Daniel; Duenser, Martin; Fritsch, Gerhard; Gradwohl-Matis, Ilse; Hartmann, Andreas; Hoelzenbein, Thomas; Jaeger, Tarkan; Landauer, Franz; Lindl, Gregor; Lux, Michael; Steindl, Johannes; Stundner, Ottokar; Szabo, Christian; Bidgoli, Jawad; Verdoodt, Hans; Forget, Patrice; Kahn, David; Lois, Fernande; Momeni, Mona; Prégardien, Caroline; Pospiech, Audrey; Steyaert, Arnaud; Veevaete, Laurent; de Kegel, Dirk; de Jongh, Karen; Foubert, Luc; Smitz, Carine; Vercauteren, Marcel; Poelaert, Jan; van Mossevelde, Veerle; Abeloos, Jacques; Bouchez, Stefaan; Coppens, Marc; de Baerdemaeker, Luc; Deblaere, Isabel; de Bruyne, Ann; Fonck, Kristine; Heyse, Bjorn; Jacobs, Tom; Lapage, Koen; Moerman, Anneliese; Neckebroek, Martine; Parashchanka, Aliaksandra; Roels, Nathalie; van den Eynde, Nancy; Vandenheuvel, Michael; Limmen, JurgenVan; Vanluchene, Ann; Vanpeteghem, Caroline; Wyffels, Piet; Huygens, Christel; Vandenbempt, Punitha; van de Velde, Marc; Dylst, Dimitri; Janssen, Bruno; Schreurs, Evelien; Aleixo, Fábia Berganton; Candido, Keulle; Batista, Hugo Dias; Guimarães, Mario; Guizeline, Jaqueline; Hoffmann, João; Lobo, Francisco Ricardo Marques; Nascimento, Vinícius; Nishiyama, Katia; Pazetto, Lucas; Souza, Daniela; Rodrigues, Rodrigo Souza; Vilela Dos Santos, Ana Maria; Jardim, Jaquelline; Sá Malbouisson, Luiz Marcelo; Silva, Joao; Nascimento Junior, Paulo do; Baio, Thalissa Hermínia; Pereira de Castro, Gabriel Isaac; Watanabe Oliveira, Henri Roger; Amendola, Cristina Prata; Cardoso, Gutemberg; Ortega, Daniela; Brotto, Ana Flavia; de Oliveira, Mirella Cristine; Réa-Neto, Álvaro; Dias, Fernando; Travi, Maria Eduarda; Zerman, Luiza; Azambuja, Pedro; Knibel, Marcos Freitas; Martins, Antonio; Almeida, William; Neto, Calim Neder; Tardelli, Maria Angela; Caser, Eliana; Machado, Marcio; Aguzzoli, Crisitiano; Baldisserotto, Sérgio; Tabajara, Fernanda Beck; Bettega, Fernanda; Rodrigues Júnior, La Hore Correa; de Gasperi, Julia; Faina, Lais; Nolasco, Marcos Farias; Ferreira da Costa Fischer, Bruna; Fosch de Campos Ferreira, Mariana; Hartmann, Cristina; Kliemann, Marta; Hubert Ribeiro, Gustavo Luis; Fraga, Julia Merladete; Netto, Thiago Motta; Pozza, Laura Valduga; Wendling, Paulo Rafael; Azevedo, Caroline; Garcia, Juliana; Lopes, Marcel; Maia, Bernardo; Maselli, Paula; Melo, Ralph; Mendes, Weslley; Neves, Matheus; Ney, Jacqueline; Piras, Claudio; Applewhaite, Christopher; Carr, Adrienne; Chow, Lorraine; Duttchen, Kaylene; Foglia, Julena; Greene, Michael; Hinther, Ashley; Houston, Kendra; McCormick, Thomas Jared; Mikhayel, Jennifer; Montasser, Sam; Ragan, Alex; Suen, Andrew; Woolsey, Adrianna; Yu, Hai Chuan; Funk, Duane; Kowalski, Stephen; Legaspi, Regina; McDonald, Heather; Siddiqui, Faisal; Pridham, Jeremy; Rowe, Bernadette; Sampson, Sonia; Thiessen, Barton; Zbitnew, Geoff; Bernard, Andre; George, Ronald; Jones, Philip; Moor, Rita; Siddiqui, Naveed; Wolfer, Alexandra; Tran, Diem; Winch, Denyse; Dobson, Gary; McCormick, Thomas; Montasser, Osama; Hall, Richard; Baghirzada, Leyla; Curley, Gerard; Dai, Si Yuan; Hare, Gregory; Lee, Esther; Shastri, Uma; Tsui, Albert; Yagnik, Anmol; Alvares, Danielle; Choi, Stephen; Dwyer, Heather; Flores, Kathrina; McCartney, Colin; Somascanthan, Priya; Carroll, Jo; Pazmino-Canizares, Janneth; Ami, Noam; Chan, Vincent; Perlas, Anahi; Argue, Ruth; Huang, Yang; Lavis, Katie; Mayson, Kelly; Cao, Ying; Gao, Hong; Hu, Tingju; Lv, Jie; Yang, Jian; Yang, Yang; Zhong, Yi; Zhou, Jing; Zou, Xiaohua; He, Miao; Li, Xiaoying; Luo, Dihuan; Wang, Haiying; Yu, Tian; Chen, Liyong; Wang, Lijun; Cai, Yunfei; Cao, Zhongming; Li, Yanling; Lian, Jiaxin; Sun, Haiyun; Wang, Sheng; Wang, Zhipeng; Wang, Kenru; Zhu, Yi; Du, Xindan; Fan, Hao; Fu, Yunbin; Huang, Lixia; Huang, Yanming; Hwan, Haifang; Luo, Hong; Qu, Pi-Sheng; Tao, Fan; Wang, Zhen; Wang, Guoxiang; Wang, Shun; Zhang, Yan; Zhang, Xiaolin; Chen, Chao; Wang, Weixing; Liu, Zhengyuan; Fan, Lihua; Tang, Jing; Chen, Yijun; Chen, Yongjie; Han, Yangyang; Huang, Changshun; Liang, Guojin; Shen, Jing; Wang, Jun; Yang, Qiuhong; Zhen, Jungang; Zhou, Haidong; Chen, Junping; Chen, Zhang; Li, Xiaoyu; Meng, Bo; Ye, Haiwang; Zhang, Xiaoyan; Bi, Yanbing; Cao, Jianqiao; Guo, Fengying; Lin, Hong; Liu, Yang; Lv, Meng; Shi, Pengcai; Song, Xiumei; Sun, Chuanyu; Sun, Yongtao; Wang, Yuelan; Wang, Shenhui; Zhang, Min; Chen, Rong; Hou, Jiabao; Leng, Yan; Meng, Qing-Tao; Qian, Li; Shen, Zi-Ying; Xia, Zhong-Yuan; Xue, Rui; Zhang, Yuan; Zhao, Bo; Zhou, Xian-Jin; Chen, Qiang; Guo, Huinan; Guo, Yongqing; Qi, Yuehong; Wang, Zhi; Wei, Jianfeng; Zhang, Weiwei; Zheng, Lina; Bao, Qi; Chen, Yaqiu; Chen, Yijiao; Fei, Yue; Hu, Nianqiang; Hu, Xuming; Lei, Min; Li, Xiaoqin; Lv, Xiaocui; Miao, Fangfang; Ouyang, Lingling; Qian, Lu; Shen, Conyu; Sun, Yu; Wang, Yuting; Wang, Dong; Wu, Chao; Xu, Liyuan; Yuan, Jiaqi; Zhang, Lina; Zhang, Huan; Zhang, Yapping; Zhao, Jinning; Zhao, Chong; Zhao, Lei; Zheng, Tianzhao; Zhou, Dachun; Zhou, Haiyan; Zhou, Ce; Lu, Kaizhi; Zhao, Ting; He, Changlin; Chen, Hong; Chen, Shasha; Cheng, Baoli; He, Jie; Jin, Lin; Li, Caixia; Li, Hui; Pan, Yuanming; Shi, Yugang; Wen, Xiao Hong; Wu, Shuijing; Xie, Guohao; Zhang, Kai; Zhao, Bing; Lu, Xianfu; Chen, Feifei; Liang, Qisheng; Lin, Xuewu; Ling, Yunzhi; Liu, Gang; Tao, Jing; Yang, Lu; Zhou, Jialong; Chen, Fumei; Cheng, Zhonggui; Dai, Hanying; Feng, Yunlin; Hou, Benchao; Gong, Haixia; Hu, Chun Hua; Huang, Haijin; Huang, Jian; Jiang, Zhangjie; Li, Mengyuan; Lin, Jiamei; Liu, Mei; Liu, Weicheng; Liu, Zhen; Liu, Zhiyi; Luo, Foquan; Ma, Longxian; Min, Jia; Shi, Xiaoyun; Song, Zhiping; Wan, Xianwen; Xiong, Yingfen; Xu, Lin; Yang, Shuangjia; Zhang, Qin; Zhang, Hongyan; Zhang, Huaigen; Zhang, Xuekang; Zhao, Lili; Zhao, Weihong; Zhao, Weilu; Zhu, Xiaoping; Bai, Yun; Chen, Linbi; Chen, Sijia; Dai, Qinxue; Geng, Wujun; Han, Kunyuan; He, Xin; Huang, Luping; Ji, Binbin; Jia, Danyun; Jin, Shenhui; Li, Qianjun; Liang, Dongdong; Luo, Shan; Lwang, Lulu; Mo, Yunchang; Pan, Yuanyuan; Qi, Xinyu; Qian, Meizi; Qin, Jinling; Ren, Yelong; Shi, Yiyi; Wang, Junlu; Wang, Junkai; Wang, Leilei; Xie, Junjie; Yan, Yixiu; Yao, Yurui; Zhang, Mingxiao; Zhao, Jiashi; Zhuang, Xiuxiu; Ai, Yanqiu; Du, Fang; He, Long; Huang, Ledan; Li, Zhisong; Li, Huijuan; Li, Yetong; Li, Liwei; Meng, Su; Yuan, Yazhuo; Zhang, Enman; Zhang, Jie; Zhao, Shuna; Ji, Zhenrong; Pei, Ling; Wang, Li; Chen, Chen; Dong, Beibei; Li, Jing; Miao, Ziqiang; Mu, Hongying; Qin, Chao; Su, Lin; Wen, Zhiting; Xie, Keliang; Yu, Yonghao; Yuan, Fang; Hu, Xianwen; Zhang, Ye; Xiao, Wangpin; Zhu, Zhipeng; Dai, Qingqing; Fu, Kaiwen; Hu, Rong; Hu, Xiaolan; Huang, Song; Li, Yaqi; Liang, Yingping; Yu, Shuchun; Guo, Zheng; Jing, Yan; Tang, Na; Wu, Jie; Yuan, Dajiang; Zhang, Ruilin; Zhao, Xiaoying; Li, Yuhong; Bai, Hui-Ping; Liu, Chun-Xiao; Liu, Fei-Fei; Ren, Wei; Wang, Xiu-Li; Xu, Guan-Jie; Hu, Na; Li, Bo; Ou, Yangwen; Tang, Yongzhong; Yao, Shanglong; Zhang, Shihai; Kong, Cui-Cui; Liu, Bei; Wang, Tianlong; Xiao, Wei; Lu, Bo; Xia, Yanfei; Zhou, Jiali; Cai, Fang; Chen, Pushan; Hu, Shuangfei; Wang, Hongfa; Xu, Qiong; Hu, Liu; Jing, Liang; Li, Bin; Liu, Qiang; Liu, Yuejiang; Lu, Xinjian; Peng, Zhen Dan; Qiu, Xiaodong; Ren, Quan; Tong, Youliang; Wang, Jin; Wen, Yazhou; Wu, Qiong; Xia, Jiangyan; Xie, Jue; Xiong, Xiapei; Xu, Shixia; Yang, Tianqin; Ye, Hui; Yin, Ning; Yuan, Jing; Zeng, Qiuting; Zhang, Baoling; Zheng, Kang; Cang, Jing; Chen, Shiyu; Fan, Yu; Fu, Shuying; Ge, Xiaodong; Guo, Baolei; Huang, Wenhui; Jiang, Linghui; Jiang, Xinmei; Liu, Yi; Pan, Yan; Ren, Yun; Shan, Qi; Wang, Jiaxing; Wang, Fei; Wu, Chi; Zhang, Xiaoguang; Christiansen, Ida Cecilie; Granum, Simon Nørgaard; Rasmussen, Bodil Steen; Daugaard, Morten; Gambhir, Rajiv; Brandsborg, Birgitte; Steingrímsdóttir, Guðný Erla; Jensen-Gadegaard, Peter; Olsen, Karsten Skovgaard; Siegel, Hanna; Eskildsen, Katrine Zwicky; Gätke, Mona Ring; Wibrandt, Ida; Heintzelmann, Simon Bisgaard; Wiborg Lange, Kai Henrik; Lundsgaard, Rune Sarauw; Amstrup-Hansen, Louise; Hovendal, Claus; Larsen, Michael; Lenstrup, Mette; Kobborg, Tina; Larsen, Jens Rolighed; Pedersen, Anette Barbre; Smith, Søren Hübertz; Oestervig, Rebecca Monett; Afshari, Arash; Andersen, Cheme; Ekelund, Kim; Secher, Erik Lilja; Beloeil, Helene; Lasocki, Sigismond; Ouattara, Alexandre; Sineus, Marlene; Molliex, Serge; Legouge, Marie Lim; Wallet, Florent; Tesniere, Antoine; Gaudin, Christophe; Lehur, Paul; Forsans, Emma; de Rudnicki, Stéphane; Maudet, Valerie Serra; Mutter, Didier; Sojod, Ghassan; Ouaissi, Mehdi; Regimbeau, Jean-Marc; Desbordes, Jacques; Comptaer, Nicolas; Manser, Diae El; Ethgen, Sabine; Lebuffe, Gilles; Auer, Patrick; Härtl, Christine; Deja, Maria; Legashov, Kirill; Sonnemann, Susanne; Wiegand-Loehnert, Carola; Falk, Elke; Habicher, Marit; Angermair, Stefan; Laetsch, Beatrix; Schmidt, Katrin; von Heymann, Christian; Ramminger, Axel; Jelschen, Florian; Pabel, Svenja; Weyland, Andreas; Czeslick, Elke; Gille, Jochen; Malcharek, Michael; Sablotzki, Armin; Lueke, Katharina; Wetzel, Peter; Weimann, Joerg; Lenhart, Franz-Peter; Reichle, Florian; Schirmer, Frederike; Hüppe, Michael; Klotz, Karl; Nau, Carla; Schön, Julika; Mencke, Thomas; Wasmund, Christina; Bankewitz, Carla; Baumgarten, Georg; Fleischer, Andreas; Guttenthaler, Vera; Hack, Yvonne; Kirchgaessner, Katharina; Männer, Olja; Schurig-Urbaniak, Marlen; Struck, Rafael; van Zyl, Rebekka; Wittmann, Maria; Goebel, Ulrich; Harris, Sarah; Veit, Siegfried; Andreadaki, Evangelia; Souri, Flora; Katsiadramis, Ioannis; Skoufi, Anthi; Vasileiou, Maria; Aimoniotou-Georgiou, Eleni; Katsourakis, Anastasios; Veroniki, Fotini; Vlachogianni, Glyceria; Petra, Konstantina; Chlorou, Dimitra; Oloktsidou, Eirini; Ourailoglou, Vasileios; Papapostolou, Konstantinos; Tsaousi, Georgia; Daikou, Panagoula; Dedemadi, Georgia; Kalaitzopoulos, Ioannis; Loumpias, Christos; Bristogiannis, Sotirios; Dafnios, Nikolaos; Gkiokas, Georgios; Kontis, Elissaios; Kozompoli, Dimitra; Papailia, Aspasia; Theodosopoulos, Theodosios; Bizios, Christol; Koutsikou, Anastasia; Moustaka, Aleaxandra; Plaitakis, Ioannis; Armaganidis, Apostolos; Christodoulopoulou, Theodora; Lignos, Mihail; Theodorakopoulou, Maria; Asimakos, Andreas; Ischaki, Eleni; Tsagkaraki, Angeliki; Zakynthinos, Spyros; Antoniadou, Eleni; Koutelidakis, Ioannis; Lathyris, Dimitrios; Pozidou, Irene; Voloudakis, Nikolaos; Dalamagka, Maria; Elena, Gkonezou; Chronis, Christos; Manolakaki, Dimitra; Mosxogiannidis, Dimitris; Slepova, Tatiana; Tsakiridou, Isaia-Sissy; Lampiri, Claire; Vachlioti, Anastasia; Panagiotakis, Christos; Sfyras, Dimitrios; Tsimpoukas, Fotios; Tsirogianni, Athanasia; Axioti, Elena; Filippopoulos, Andreas; Kalliafa, Elli; Kassavetis, George; Katralis, Petros; Komnos, Ioannis; Pilichos, Georgios; Ravani, Ifigenia; Totis, Antonis; Apagaki, Eymorfia; Efthymiadi, Andromachi; Kampagiannis, Nikolaos; Paraforou, Theoniki; Tsioka, Agoritsa; Georgiou, Georgios; Vakalos, Aristeidis; Bairaktari, Aggeliki; Charitos, Efthimios; Markou, George; Niforopoulou, Panagiota; Papakonstantinou, Nikolaos; Tsigou, Evdoxia; Xifara, Archontoula; Zoulamoglou, Menelaos; Gkioni, Panagiota; Karatzas, Stylianos; Kyparissi, Aikaterini; Mainas, Efstratios; Papapanagiotou, Ioannis; Papavasilopoulou, Theonymfi; Fragandreas, George; Georgopoulou, Eleni; Katsika, Eleni; Psarras, Kyriakos; Synekidou, Eirini; Verroiotou, Maria; Vetsiou, Evangelia; Zaimi, Donika; Anagnou, Athina; Apostolou, Konstantinos; Melissopoulou, Theodora; Rozenberg, Theophilos; Tsigris, Christos; Boutsikos, Georgios; Kalles, Vasileios; Kotsalas, Nikolaos; Lavdaiou, Christina; Paikou, Fotini; Panagou, Georgia-Laura; Spring, Anna; Botis, Ioannis; Drimala, Maria; Georgakakis, Georgios; Kiourtzieva, Ellada; Ntouma, Panagiota; Prionas, Apostolos; Xouplidis, Kyriakos; Dalampini, Eleftheria; Giannaki, Chrysavgi; Iasonidou, Christina; Ioannidis, Orestis; Lavrentieva, Athina; Lavrentieva, Athena; Papageorgiou, George; Kokkinoy, Maria; Stafylaraki, Maria; Gaitanakis, Stylianos; Karydakis, Periclis; Paltoglou, Josef; Ponireas, Panagiotis; Chaloulis, Panagiotis; Provatidis, Athanasios; Sousana, Anisoglou; Gardikou, Varvara Vanessa; Konstantivelli, Maria; Lataniotou, Olga; Lisari, Elisavet; Margaroni, Maria; Stamatiou, Konstantinos; Nikolaidis, Edouardos; Pnevmatikos, Ioannis; Sertaridou, Eleni; Andreou, Alexandros; Arkalaki, Eleni; Athanasakis, Elias; Chaniotaki, Fotini; Chatzimichali, Chatzimichali Aikaterini; Christofaki, Maria; Dermitzaki, Despina; Fiorentza, Klara; Frantzeskos, Georgios; Geromarkaki, Elisavet; Kafkalaki, Kalliopi; Kalogridaki, Marina; Karydi, Konstyllia; Kokkini, Sofia; Kougentakis, Georgios; Lefaki, Tatiana; Lilitsis, Emmanouhl; Makatounaki, Aikaterini; Malliotakis, Polychronis; Michelakis, Dimosthenis; Neonaki, Maria; Nyktari, Vasileia; Palikyra, Iliana; Papadakis, Eleftherios; Papaioannou, Alexandra; Sfakianakis, Konstantinos; Sgouraki, Maria; Souvatzis, Xenia; Spartinou, Anastasia; Stefanidou, Nefeli; Syrogianni, Paulina; Tsagkaraki, Georgia; Arnaoutoglou, Elena; Arnaoutoglou, Christina; Bali, Christina; Bouris, Vasilios; Doumos, Rodamanthos; Gkini, Konstantia-Paraskevi; Kapaktsi, Clio; Koulouras, Vasilios; Lena, Arian; Lepida, Dimitra; Michos, Evangelos; Papadopoulos, Dimitrios; Paschopoulos, Minas; Rompou, Vaia Aliki; Siouti, Ioanna; Tsampalas, Stavros; Ververidou, Ourania; Zilis, Georgios; Charlalampidoy, Alexandra; Christodoulidis, Gregory; Flossos, Andreas; Stamoulis, Konstantinos; Chan, Matthew; Tsang, Man Shing Caleb; Tsang, Man Shing; Lai, Man Ling; Yip, Chi Pang; Heymans Chan, Hey Man; Law, Bassanio; Li, Wing Sze; Chu, Hiu Man; Koo, Emily Gar Yee; Lam, Chi Cheong Joe; Cheng, Ka Ho; Lam, Tracy; Chu, Susanna; Lam, Wing Yan; Wong, Kin Wai Kevin; Kwok, Dilys; Hung, Ching Yue Janice; Chan, Wai Kit Jacky; Wong, Wing Lam; Chung, Chun Kwong Eric; Ma, Shu Kai; Kaushik, Shuchi; Shah, Bhagyesh; Shah, Dhiren; Shah, Sanjay; Ar, Praburaj; Muthuchellappan, Radhakrishnan; Agarwal, Vandana; Divatia, Jigeeshu; Mishra, Sanghamitra; Nimje, Ganesh; Pande, Swati; Savarkar, Sukhada; Shrivastava, Aditi; Thomas, Martin; Yegnaram, Shashikant; Hidayatullah, Rahmat; Puar, Nasman; Niman, Sumara; Indra, Imai; Hamzah, Zulkarnain; Yuliana, Annika; Abidin, Ucu Nurhadiat; Dursin, Ade Nurkacan; Kurnia, Andri; Susanti, Ade; Handayani, Dini; Alit, Mahaalit Aribawa; Arya, Aryabiantara; Senapathi, Tjokorda Gde Agung; Utara, Utara Hartawan; Wid, Widnyana Made; Wima, Semarawima; Wir, Wiryana Made; Jehosua, Brillyan; Kaunang, Jonathan; Lantang, Eka Yudha; Najoan, Rini; Waworuntu, Neil; Awad, Hadi; Fuad, Akram; Geddoa, Burair; Khalaf, Abdel Razzaq; Al Hussaini, Sabah; Albaj, Safauldeensalem; Kenber, Maithem; Bettinelli, Alessandra; Spadaro, Savino; AlbertoVolta, Carlo; Giancarlo, Luigi; Sottosanti, Vicari; Copetti, Elisa; Spagnesi, Lorenzo; Toretti, Ilaria; Alloj, Chiara; Cardellino, Silvano; Carmino, Livio; Costanzo, Eleonora; Fanfani, Lucia Caterina; Novelli, Maria Teresa; Roasio, Agostino; Bellandi, Mattia; Beretta, Luigi; Bignami, Elena; Bocchino, Speranza; Cabrini, Luca; Corti, Daniele; Landoni, Giovanni; Meroni, Roberta; Moizo, Elena; Monti, Giacomo; Pintaudi, Margherita; Plumari, Valentina Paola; Taddeo, Daiana; Testa, Valentina; Winterton, Dario; Zangrillo, Alberto; Cloro, Luigi Maria; Colangelo, Chiara; Colangelo, Antonio; Rotunno, Giuseppe; Paludi, Miguel Angel; Maria, Cloro Paolo; Pata, Antonio; Parrini, Vieri; Gatta, Alessandro; Nastasi, Mauro; Tinti, Carla; Baroselli, Antonio; Arrigo, Mario; Benevento, Angelo; Bottini, Corrado; Cannavo', Maurizio; Gastaldi, Christian; Marchesi, Alessandro; Pascazio, Angelantonio; Pata, Francesco; Pozzi, Emilio; Premoli, Alberto; Tessera, Gaetano; Boschi, Luca; D'Andrea, Rocco; Ghignone, Federico; Poggioli, Gilberto; Sibilio, Andrea; Taffurelli, Mario; Ugolini, Giampaolo; Ab Majid, Mohd Azuan; Ab Rahman, Rusnah; Joseph, James; Pathan, Furquan; Sybil Shah, Mohammad Hafizshah; Yap, Huey Ling; Cheah, Seleen; Chin, Im Im; Looi, Ji Keon; Tan, Siew Ching; Visvalingam, Sheshendrasurian; Kwok, Fan Yin; Lee, Chew Kiok; Tan, Tse Siang; Wong, Sze Meng; Abdullah, Noor Hairiza; Liew, Chiat Fong; Luxuman, Lovenia; Mohd Zin, Nor Hafizah; Norddin, Muhamad Faiz; Raja Alias, Raja Liza; Wong, Juan Yong; Yong, Johnny; Bin Mustapha, Mohd Tarmimi; Chan, Weng Ken; Dzulkipli, Norizawati; Kuan, Pei Xuan; Lee, Yew Ching; Alias, Anita; Guok, Eng Ching; Jee, Chiun Chen; Ramon, Brian Rhadamantyne; Wong, Cheng Weng; Abd Ghafar, Fara Nur Idayu; Aziz, Faizal Zuhri; Hussain, Nabilah; Lee, Hooi Sean; Sukawi, Ismawaty; Woon, Yuan Liang; Abd Hadi, Husni Zaeem; Ahmad Azam, Ummi Azmira; Alias, Abdul Hafiz; Kesut, Saiful Aizar; Lee, Jun May; Ooi, Dar Vin; Sulaiman, Hetty Ayuni; Lih, Tengku Alini Tengku; Veerakumaran, Jeyaganesh; Rojas, Eder; Resendiz, Gerardo Esteban Alvarez; Zapata, Darcy Danitza Mari; López, Julio Cesar Jesús Aguilar; Flores, Armando Adolfo Alvarez; Amador, Juan Carlos Bravo; Avila, Erendira Jocelin Dominguez; Aquino, Laura Patricia González; Rodriguez, Ricardo Lopez; Landa, Mariana Torres; Urias, Emma; Hollmann, Markus; Hulst, Abraham; Preckel, Benedikt; Koopman-van Gemert, Ankie; Buise, Marc; Tolenaar, Noortje; Weber, Eric; de Fretes, Jennifer; Houweling, Peter; Ormskerk, Patricia; van Bommel, Jasper; Lance, Marcus; Smit-Fun, Valerie; van Zundert, Tom; Baas, Peter; Donald de Boer, Hans; Sprakel, Joost; Elferink-Vonk, Renske; Noordzij, Peter; van Zeggeren, Laura; Brand, Bastiaan; Spanjersberg, Rob; ten Bokkel-Andela, Janneke; Numan, Sandra; van Klei, Wilton; van Zaane, Bas; Boer, Christa; van Duivenvoorde, Yoni; Hering, Jens Peter; van Rossum, Sylvia; Zonneveldt, Harry; Campbell, Doug; Hoare, Siobhan; Santa, Sahayam; Ali, Marlynn; Allen, Sara Jane; Bell, Rachel; Choi, Hyun-Min David; Drake, Matthew; Farrell, Helen; Hayes, Katia; Higgie, Kushlin; Holmes, Kerry; Jenkins, Nicole; Kim, Chang Joon; Kim, Steven; Law, Kiew Chai; McAllister, Davina; Park, Karen; Pedersen, Karen; Pfeifer, Leesa; Pozaroszczyk, Anna; Salmond, Timothy; Steynor, Martin; Tan, Michael; Waymouth, Ellen; Ab Rahman, Ahmad Sufian; Armstrong, John; Dudson, Rosie; Jenkins, Nia; Nilakant, Jayashree; Richard, Seigne; Virdi, Pardeep; Dixon, Liane; Donohue, Roana; Farrow, Mehreen; Kennedy, Ross; Marissa, Henderson; McKellow, Margie; Nicola, Delany; Pascoe, Rebecca; Roberts, Stephen John; Rowell, George; Sumner, Matthew; Templer, Paul; Chandrasekharan, Shardha; Fulton, Graham; Jammer, Ib; More, Richard; Wilson, Leona; Chang, Yuan Hsuan; Foley, Julia; Fowler, Carolyn; Panckhurst, Jonathan; Sara, Rachel; Stapelberg, Francois; Cherrett, Veronica; Ganter, Donna Louise; McCann, Lloyd; Gilmour, Fiona; Lumsden, Rachelle; Moores, Mark; Olliff, Sue; Sardareva, Elitza; Tai, Joyce; Wikner, Matthew; Wong, Christopher; Chaddock, Mark; Czepanski, Carolyn; McKendry, Patrick; Polakovic, Daniel; Polakovich, Daniel; Robert, Axe; Belda, Margarita Tormo; Norton, Tracy; Alherz, Fadhel; Barneto, Lisa; Ramirez, Alberto; Sayeed, Ahmed; Smith, Nicola; Bennett, Cambell; McQuoid, Shane; Jansen, Tracy-Lee; Nico, Zin; Scott, John; Freschini, David; Freschini, Angela; Hopkins, Brian; Manson, Lara; Stoltz, Deon; Bates, Alexander; Davis, Simon; Freeman, Victoria; McGaughran, Lynette; Williams, Maya; Sharma, Swarna Baskar; Burrows, Tom; Byrne, Kelly; English, Duane; Johnson, Robert; Manikkam, Brendon; Naidoo, Shaun; Rumball, Margot; Whittle, Nicola; Franks, Romilla; Gibson-Lapsley, Hannah; Salter, Ryan; Walsh, Dean; Cooper, Richard; Perry, Katherine; Obobolo, Amos; Sule, Umar Musa; Ahmad, Abdurrahman; Atiku, Mamuda; Mohammed, Alhassan Datti; Sarki, Adamu Muhammad; Adekola, Oyebola; Akanmu, Olanrewaju; Durodola, Adekunle; Olukoju, Olusegun; Raji, Victor; Olajumoke, Tokunbo; Oyebamiji, Emmanuel; Adenekan, Anthony; Adetoye, Adedapo; Faponle, Folayemi; Olateju, Simeon; Owojuyigbe, Afolabi; Talabi, Ademola; Adenike, Odewabi; Adewale, Badru; Collins, Nwokoro; Ezekiel, Emmanuel; Fatungase, Oluwabunmi Motunrayo; Grace, Anuforo; Sola, Sotannde; Stella, Ogunmuyiwa; Ademola, Adeyinka; Adeolu, Augustine A.; Adigun, Tinuola; Akinwale, Mukaila; Fasina, Oluyemi; Gbolahan, Olalere; Idowu, Olusola; Olonisakin, Rotimi Peter; Osinaike, Babatunde Babasola; Asudo, Felicia; Mshelia, Danladi; Abdur-Rahman, Lukman; Agodirin, Olayide; Bello, Jibril; Bolaji, Benjamin; Oyedepo, Olanrewaju Olubukola; Ezike, Humphrey; Iloabachie, Ikechukwu; Okonkwo, Ikemefuna; Onuora, Elias; Onyeka, Tonia; Ugwu, Innocent; Umeh, Friday; Alagbe-Briggs, Olubusola; Dodiyi-Manuel, Amabra; Echem, Richard; Obasuyi, Bright; Onajin-Obembe, Bisola; Bandeira, Maria Expedito; Martins, Alda; Tomé, Miguel; Costa, Ana Cristina Miranda Martins; Krystopchuk, Andriy; Branco, Teresa; Esteves, Simao; Melo, Marco António; Monte, Júlia; Rua, Fernando; Martins, Isabel; Pinho-Oliveira, Vítor Miguel; Rodrigues, Carla Maria; Cabral, Raquel; Marques, Sofia; Rêgo, Sara; Jesus, Joana Sofia Teixeira; Marques, Maria Conceição; Romao, Cristina; Dias, Sandra; Santos, Ana Margarida; Alves, Maria Joao; Salta, Cristina; Cruz, Salome; Duarte, Célia; Paiva, António Armando Furtado; Cabral, Tiago do Nascimento; Faria E Maia, Dionisio; Correia da Silva, Rui Freitas Mendonça; Langner, Anuschka; Resendes, Hernâni Oliveira; Soares, Maria da Conceição; Abrunhosa, Alexandra; Faria, Filomena; Miranda, Lina; Pereira, Helena; Serra, Sofia; Ionescu, Daniela; Margarit, Simona; Mitre, Calin; Vasian, Horatiu; Manga, Gratiela; Stefan, Andreea; Tomescu, Dana; Filipescu, Daniela; Paunescu, Marilena-Alina; Stefan, Mihai; Stoica, Radu; Gavril, Laura; Pătrășcanu, Emilia; Ristescu, Irina; Rusu, Daniel; Diaconescu, Ciresica; Iosep, Gabriel Florin; Pulbere, Dorin; Ursu, Irina; Balanescu, Andreea; Grintescu, Ioana; Mirea, Liliana; Rentea, Irina; Vartic, Mihaela; Lupu, Mary-Nicoleta; Stanescu, Dorin; Streanga, Lavinea; Antal, Oana; Hagau, Natalia; Patras, Dumitru; Petrisor, Cristina; Tosa, Flaviu; Tranca, Sebastian; Copotoiu, Sanda Maria; Ungureanu, Liviu Lucian; Harsan, Cristian Remus; Papurica, Marius; Cernea, Daniela Denisa; Dragoescu, Nicoleta Alice; CarmenVaida, Laura Aflori; Ciobotaru, Oana Roxana; Aignatoaie, Mariana; Carp, Cristina Paula; Cobzaru, Isabelle; Mardare, Oana; Purcarin, Bianca; Tutunaru, Valentin; Ionita, Victor; Arustei, Mirela; Codita, Anisoara; Busuioc, Mihai; Chilinciuc, Ion; Ciobanu, Cristina; Belciu, Ioana; Tincu, Eugen; Blaj, Mihaela; Grosu, Ramona-Mihaela; Sandu, Gigel; Bruma, Dana; Corneci, Dan; Dutu, Madalina; Krepil, Adriana; Copaciu, Elena; Dumitrascu, Clementina Oana; Jemna, Ramona; Mihaescu, Florentina; Petre, Raluca; Tudor, Cristina; Ursache, Elena; Kulikov, Alexander; Lubnin, Andrey; Grigoryev, Evgeny; Pugachev, Stanislav; Tolmasov, Alexander; Hussain, Ayyaz; Ilyina, Yana; Roshchina, Anna; Iurin, Aleksandr; Chazova, Elena; Dunay, Artem; Karelov, Alexey; Khvedelidze, Irina; Voldaeva, Olga; Belskiy, Vladislav; Dzhamullaev, Parvin; Grishkowez, Elena; Kretov, Vladimir; Levin, Valeriy; Molkov, Aleksandr; Puzanov, Sergey; Samoilenko, Aleksandr; Tchekulaev, Aleksandr; Tulupova, Valentina; Utkin, Ivan; Allorto, Nikki Leigh; Bishop, David Gray; Builu, Pierre Monji; Cairns, Carel; Dasrath, Ashish; de Wet, Jacques; Hoedt, Marielle den; Grey, Ben; Hayes, Morgan Philip; Küsel, Belinda Senta; Shangase, Nomcebo; Wise, Robert; Cacala, Sharon; Farina, Zane; Govindasamy, Vishendran; Kruse, Carl-Heinz; Lee, Carolyn; Marais, Leonard; Naidoo, Thinagrin Dhasarthun; Rajah, Chantal; Rodseth, Reitze Nils; Ryan, Lisa; von Rhaden, Richard; Adam, Suwayba; Alphonsus, Christella; Ameer, Yusuf; Anderson, Frank; Basanth, Sujith; Bechan, Sudha; Bhula, Chettan; Biccard, Bruce M.; Biyase, Thuli; Buccimazza, Ines; Cardosa, Jorge; Chen, James; Daya, Bhavika; Drummond, Leanne; Elabib, Ali; Abdel Goad, Ehab Helmy; Goga, Ismail E.; Goga, Riaz; Harrichandparsad, R.; Hodgson, Richard E.; Jordaan, J.; Kalafatis, Nicky; Kampik, Christian; Landers, A. T.; Loots, Emil; Madansein, Rajhmum; Madaree, Anil; Madiba, Thandinkosi E.; Manzini, Vukani T.; Mbuyisa, Mbali; Moodley, Rajan; Msomi, Mduduzi; Mukama, Innocent; Naidoo, Desigan; Naidoo, Rubeshan; Naidu, Tesuven K.; Ntloko, Sindiswa; Padayachee, Eneshia; Padayachee, Lucelle; Phaff, Martijn; Pillay, Bala; Pillay, Desigan; Pillay, Lutchmee; Ramnarain, Anupa; Ramphal, Suren R.; Ryan, Paul; Saloojee, Ahmed; Sebitloane, Motshedisi; Sigcu, Noluyolo; Taylor, Jenna L.; Torborg, Alexandra; Visser, Linda; Anderson, Philip; Conradie, Alae; de Swardt, Mathew; de Villiers, Martin; Eikman, Johan; Liebenberg, Riaan; Mouton, Johan; Paton, Abbey; van der Merwe, Louwrence; Wilscott-Davids, Candice; Barrett, Wendy Joan; Bester, Marlet; de Beer, Johan; Geldenhuys, Jacques; Gouws, Hanni; Potgieter, Jan-Hendrik; Strydom, Magdel; WilberforceTurton, Edwin; Chetty, Rubendraj R.; Chirkut, Subash; Cronje, Larissa; de Vasconcellos, Kim; Dube, Nokukhanya Z.; Gama, N. Sibusiso; Green, Garyth M.; Green-Thompson, Randolph; Kinoo, Suman Mewa; Kistnasami, Prenolin; Maharaj, Kapil; Moodley, Manogaran S.; Mothae, Sibongile J.; Naidoo, Ruvashni; Aslam F Noorbhai, M.; Rughubar, Vivesh; Reddy, Jenendhiran; Singh, Avesh; Skinner, David L.; Smith, Murray J.; Singh, Bhagwan; Misra, Ravi; Naidoo, Maheshwar; Ramdharee, Pireshin; Selibea, Yvonne; Sewpersad, Selina; Sham, Shailendra; Wessels, Joseph D.; Africander, Cucu; Bejia, Tarek; Blakemore, Stephen P.; Botes, Marisa; Bunwarie, Bimalshakth; Hernandez, Carlos B.; Jeeraz, Mohammud A.; Legutko, Dagmara A.; Lopez, Acela G.; de Meyer, Jenine N.; Muzenda, Tanaka; Naidoo, Noel; Patel, Maryam; Pentela, Rao; Junge, Marina; Mansoor, Naj; Rademan, Lana; Scislowski, Pawel; Seedat, Ismail; van den Berg, Bianca; van der Merwe, Doreen; van Wyk, Steyn; Govender, Komalan; Naicker, Darshan; Ramjee, Rajesh; Saley, Mueen; Kuhn, Warren Paul; Matos-Puig, Roel; Alberto Lisi, Zaheer Moolla; Perez, Gisela; Beltran, Anna Valle; Lozano, Angels; Navarro, Carlos Delgado; Duca, Alejandro; Ernesto, Ernesto Pastor Martinez; Ferrando, Carlos; Fuentes, Isabel; García-Pérez, Maria Luisa; Gracia, Estefania; Palomares, Ana Izquierdo; Katime, Antonio; Miñana, Amanda; Incertis, Raul Raul; Romero, Esther; Romero Garcia, Carolina Soledad; Rubio, Concepcion; Artiles, Tania Socorro; Soro, Marina; Valls, Paola; Laguarda, Gisela Alaman; Benavent, Pau; Cuenca, Vicente Chisbert; Cueva, Andreu; Lafuente, Matilde; Parra, Asuncion Marques; Rodrigo, Alejandra Romero; Sanchez-Morcillo, Silvia; Tormo, Sergi; Redondo, Francisco Javier; de Andrés Ibanez, José Antonio; Diago, Lorena Gómez; José Hernández Cádiz, Maria; Manuel, Granell Gil; Peris, Raquel; Saiz, Cristina; Vivo, Jose Tatay; Soto, Maria Teresa Tebar; Brunete, Tamara; Cancho, David; Delgado García, David R.; Zamudio, Diana; del Valle, Santiago Garcia; Serrano, M. Luz; Alonso, Eduardo; Anillo, Victor; Maseda, Emilio; Salgado, Patricia; Suarez, Luis; Suarez-de-la-Rica, Alejandro; Villagrán, María José; Alonso, José Ignacio; Cabezuelo, Estefania; Garcia-Saiz, Irene; Lopez del Moral, Olga; Martín, Silvia; Gonzalez, Alba Perez; Doncel, Ma Sherezade Tovar; Vera, Martin Agüero; José Ávila Sánchez, Francisco; Castaño, Beatriz; Moreira, Beatriz Castaño; Risco, Sahely Flores; Martín, Daniel Paz; Martín, Fernando Pérez; Poza, Paloma; Ruiz, Adela; Serna Martínez, Wilson Fabio; Vicente, Bárbara Vázquez; Dominguez, Saul Velaz; Fernández, Salvador; Munoz-López, Alfonso; Bernat, Maria Jose; Mas, Arantxa; Planas, Kenneth; Jawad, Monir; Saeed, Yousif; Hedin, Annika; Levander, Helena; Holmström, Sandra; Lönn, David; Zoerner, Frank; Åkring, Irene; Widmark, Carl; Zettergren, Jan; Liljequist, Victor Aspelund; Nystrom, Lena; Odeberg-Wernerman, Suzanne; Oldner, Anders; Fagerlund, Malin Jonsson; Reje, Patrik; Lyckner, Sara; Sperber, Jesper; Adolfsson, Anne; Klarin, Bengt; Ögren, Katrin; Barras, Jean-Pierre; Bührer, Thomas; Despotidis, Vasileios; Helmy, Naeder; Holliger, Stephan; Raptis, Dimitri Aristotle; Schmid, Roger; Meyer, Antoine; Jaquet, Yves; Kessler, Ulf; Muradbegovic, Mirza; Nahum, Solange R.; Rotunno, Teresa; Schiltz, Boris; Voruz, François; Worreth, Marc; Christoforidis, Dimitri; Popeskou, Sotirios Georgios; Furrer, Markus; Prevost, Gian Andrea; Stocker, Andrea; Lang, Klaus; Breitenstein, Stefan; Ganter, Michael T.; Geisen, Martin; Soll, Christopher; Korkmaz, Michelle; Lubach, Iris; Schmitz, Michael; Meyer Zu Schwabedissen, Moritz; Moritz, Meyer Zu Schwabedissen; Zingg, Urs; Hillermann, Thomas; Wildi, Stefan; Pinto, Bernardo Bollen; Walder, Bernhard; Mariotti, Giustina; Slankamenac, Ksenija; Namuyuga, Mirioce; Kyomugisha, Edward; Kituuka, Olivia; Shikanda, Anne Wesonga; Kakembo, Nasser; Tom, Charles Otim; Antonina, Webombesa; Bua, Emmanuel; Ssettabi, Eden Michael; Epodoi, Joseph; Kabagenyi, Fiona; Kirya, Fred; Dempsey, Ged; Seasman, Colette; Nawaz Khan, Raja Basit; Kurasz, Claire; Macgregor, Mark; Shawki, Burhan; Francis, Daren; Hariharan, Vimal; Chau, Simon; Ellis, Kate; Butt, Georgina; Chicken, Dennis-Wayne; Christmas, Natasha; Allen, Samantha; Daniel, Gayatri Daniel; Dempster, Angie; Kemp, Juliette; Matthews, Lewis; Mcglone, Philip; Tambellini, Joanne; Trodd, Dawn; Freitas, Katie; Garg, Atul; Gupta, Janesh Kumar; Karpate, Shilpaja; Kulkarni, Aditi; O'Hara, Chloe; Troko, Jtroko; Angus, Kirsty; Bradley, Jacqueline; Brennan, Emma; Brooks, Carolyn; Brown, Janette; Brown, Gemma; Finch, Amanda; Gratrix, Karen; Hesketh, Sue; Hill, Gillian; Jeffs, Carol; Morgan, Maureen; Pemberton, Chris; Slawson, Nicola; Spickett, Helen; Swarbrick, Gemma; Thomas, Megan; van Duyvenvoorde, Greta; Brennan, Andrew; Briscoe, Richard; Cooper, Sarah; Lawton, Tom; Northey, Martin; Senaratne, Rashmi; Stanworth, Helen; Burrows, Lorna; Cain, Helen; Craven, Rachael; Davies, Keith; Jonas, Attila; Pachucki, Marcin; Walkden, Graham; Davies, Helen; Gudaca, Mariethel; Hobrok, Maria; Arawwawala, Dilshan; Fergey, Lauren; Gardiner, Matthew; Gunn, Jacqueline; Johnson, Lyndsay; Lofting, Amanda; Lyle, Amanda; Neela, Fiona Mc; Smolen, Susan; Topliffe, Joanne; Williams, Sarah; Bland, Martin; Balaji, Packianathaswamy; Kaura, Vikas; Lanka, Prasad; Smith, Neil; Ahmed, Ahmed; Myatt, John; Shenoy, Ravikiran; Soon, Wai Cheong; Tan, Jessica; Karadia, Sunny; Self, James; Durant, Emma; Tripathi, Shiva; Bullock, Clare; Campbell, Debbie; Ghosh, Alison; Hughes, Thomas; Zsisku, Lajos; Bengeri, Sheshagiri; Cowton, Amanda; Khalid, Mohammed Shazad; Limb, James; McAdam, Colin; Porritt, Mandy; Rafi, M. Amir; Shekar, Priya; Adams, David; Harden, Catherine; Hollands, Heidi; King, Angela; March, Linda; Minto, Gary; Patrick, Abigail; Squire, Rosalyn; Waugh, Darren; Kumara, Paramesh; Simeson, Karen; Yarwood, Jamie; Browning, Julie; Hatton, Jonathan; Julian, Howes; Mitra, Atideb; Newton, Maria; Pernu, Pawan Kootelu; Wilson, Alison; Commey, Thelma; Foot, Helen; Glover, Lyn; Gupta, Ajay; Lancaster, Nicola; Levin, Jill; Mackenzie, Felicity; Mestanza, Claire; Nofal, Emma; Pout, Lauren; Varden, Rosanna; Wild, Jonathan; Jones, Stephanie; Moreton, Sarah; Pulletz, Mark; Davies, Charlotte; Martin, Matthew; Thomas, Sian; Burns, Karen; McArthur, Carol; Patel, Panna; Lau, Gary; Rich, Natalie; Davis, Fiona; Lyons, Rachel; Port, Beth; Prout, Rachel; Smith, Christopher; Adelaja, Yemi; Bennett, Victoria; Bidd, Heena; Dumitrescu, Alexandra; Murphy, Jacqui Fox; Keen, Abigail; Mguni, Nhlanhla; Ong, Cheng; Adams, George; Boshier, Piers; Brown, Richard; Butryn, Izabella; Chatterjee, Jayanta; Freethy, Alexander; Lockwood, Geoffrey; Tsakok, Maria; Tsiligiannis, Sophia; Peat, William; Stephenson, Lorraine; Bradburn, Mike; Pick, Sara; Cunha, Pedro; Olagbaiye, Olufemi; Tayeh, Salim; Packianathaswamy, Balaji; Abernethy, Caroline; Balasubramaniam, Madhu; Bennett, Rachael; Bolton, David; Martinson, Victoria; Naylor, Charde; Bell, Stephanie; Heather, Blaylock; Kushakovsky, Vlad; Alcock, Liam; Alexander, Hazel; Anderson, Colette; Baker, Paul; Brookes, Morag; Cawthorn, Louise; Cirstea, Emanuel; Clarkson, Rachel; Colling, Kerry; Coulter, Ian; Das, Suparna; Haigh, Kathryn; Hamdan, Alhafidz; Hugill, Keith; Kottam, Lucksy; Lisseter, Emily; Mawdsley, Matthew; McGivern, Julie; Padala, Krishnaveni; Phelps, Victoria; Ramesh Kumar, Vineshykaa; Stewart, Kirsten; Towse, Kayley; Tregonning, Julie; Vahedi, Ali; Walker, Alycon; Baines, Duncan; Bilolikar, Anjali; Chande, Shiv; Copley, Edward; Dunk, Nigel; Kulkarni, Raghavendra; Kumar, Pawan; Metodiev, Yavor; Ncomanzi, Dumisani; Raithatha, Bhavesh; Raymode, Parizade; Szafranski, Jan; Twohey, Linda; Watt, Philip; Weatherall, Lucie; Weatherill, J.; Whitman, Zoe; Wighton, Elinor; Abayasinghe, Chamika; Chan, Alexander; Darwish, Sharif; Gill, James; Glasgow, Emma; Hadfield, Daniel; Harris, Clair; Hopkins, Phil; Kochhar, Arun; Kunst, Gudrun; Mellis, Clare; Pool, Andrew; Riozzi, Paul; Selman, Andrew; Smith, Emma-Jane; Vele, Liana; Gercek, Yuksel; Guy, Kramer; Holden, Douglas; Watson, Nicholas; Whysall, Karen; Andreou, Prematie; Hales, Dawn; Thompson, Jonathan; Bowrey, Sarah; McDonald, Shara; Gilmore, Jemma; Hills, Vicky; Kelly, Chan; Kelly, Sinead; Lloyd, Geraint; Abbott, Tom; Gall, Lewis; Torrance, Hew; Vivian, Mark; Berntsen, Emer; Nolan, Tracey; Turner, Angus; Vohra, Akbar; Brown, Andrew; Clark, Richard; Coughlan, Elaine; Daniel, Conway; Patvardhan, Chinmay; Pearson, Rachel; Predeep, Sheba; Saad, Hesham; Shanmugam, Mohanakrishnan; Varley, Simon; Wylie, Katharine; Cooper, Lucy; Makowski, Arystarch; Misztal, Beata; Moldovan, Eliza; Pegg, Claire; Donovan, Andrew; Foot, Jayne; Large, Simon; Claxton, Andrew; Netke, Bhagyashree; Armstrong, Richard; Calderwood, Claire; Kwok, Andy; Mohr, Otto; Oyeniyi, Peter; Patnaik, Lisa; Post, Benjamin; Ali, Sarah; Arshad, Homa; Baker, Gerard; Brenner, Laura; Brincat, Maximilian; Brunswicker, Annemarie; Cox, Hannah; Cozar, Octavian Ionut; Cheong, Edward; Durst, Alexander; Fengas, Lior; Flatt, Jim; Glister, Georgina; Narwani, Vishal; Photi, Evangelos; Rankin, Adeline; Rosbergen, Melissa; Tan, Mark; Beaton, Ceri; Horn, Rachel; Hunt, Jane; Rousseau, Guy; Stancombe, Lucia; Absar, Mohammed; Allsop, Joanne; Drinkwater, Zoe; Hodgkiss, Tracey; Smith, Kirsty; Brown, Jamie; Alexander-Sefre, Farhad; Campey, Lorraine; Dudgeon, Lucy; Hall, Kathryn; Hitchcock, Rachael; James, Lynne; Smith, Kate; Winstone, Ulrika; Ahmad, Norfaizan; Bauchmuller, Kris; Harrison, Jonathan; Jeffery, Holly; Miller, Duncan; Pinder, Angela; Pothuneedi, Sailaja; Rosser, Jonathan; Sanghera, Sumayer; Swift, Diane; Walker, Rachel; Bester, Delia; Cavanagh, Sarah; Cripps, Heather; Daniel, Harvey; Lynch, Julie; Paton, Alison; Pyke, Shirley; Scholefield, John; Whitworth, Helen; Bottrill, Fiona; Ramalingam, Ganesh; Webb, Stephen; Akerman, Nik; Antill, Philip; Bourner, Lynsey; Buckley, Sarah; Castle, Gail; Charles, Rob; Eggleston, Christopher; Foster, Rebecca; Gill, Satwant; Lindley, Kate; Lklouk, Mohamed; Lowery, Tracey; Martin, Oliver; Milne, David; O'Connor, Patrick; Ratcliffe, Andrew; Rose, Alastair; Smith, Annie; Varma, Sandeep; Ward, Jackie; Barcraft-Barnes, Helena; Camsooksai, Julie; Colvin, Carolyn; Reschreiter, Henrik; Tbaily, Lee; Venner, Nicola; Hamilton, Caroline; Kelly, Lewis; Toth-Tarsoly, Piroska; Dodsworth, Kerry; Foord, Denise; Gordon, Paul; Hawes, Elizabeth; Lamb, Nikki; Mouland, Johanna; Nightingale, Jeremy; Rose, Steve; Schrieber, Joe; Al'Amri, Khalid; Aladin, Hafiz; Arshad, Mohammed Asif; Barraclough, James; Bentley, Conor; Bergin, Colin; Carrera, Ronald; Clarkson, Aisling; Collins, Michelle; Cooper, Lauren; Denham, Samuel; Griffiths, Ewen; Ip, Peter; Jeyanthan, Somasundaram; Joory, Kavita; Kaur, Satwant; Marriott, Paul; Mitchell, Natalie; Nagaiah, Sukumar; Nilsson, Annette; Parekh, Nilesh; Pope, Martin; Seager, Joseph; Serag, Hosam; Tameem, Alifia; Thomas, Anna; Thunder, Joanne; Torrance, Andrew; Vohra, Ravinder; Whitehouse, Arlo; Wong, Tony; Blunt, Mark; Wong, Kate; Giles, Julian; Reed, Isabelle; Weller, Debbie; Bell, Gillian; Birch, Julie; Damant, Rose; Maiden, Jane; Mewies, Clare; Prince, Claire; Radford, Jane; Reynolds, Tim; Balain, Birender; Banerjee, Robin; Barnett, Andrew; Burston, Ben; Davies, Kirsty; Edwards, Jayne; Evans, Chris; Ford, David; Gallacher, Pete; Hill, Simon; Jaffray, David; Karlakki, Sudheer; Kelly, Cormac; Kennedy, Julia; Kiely, Nigel; Lewthwaite, Simon; Marquis, Chris; Ockendon, Matthew; Phillips, Stephen; Pickard, Simon; Richardson, James; Roach, Richard; Smith, Tony; Spencer-Jones, Richard; Steele, Niall; Steen, Julie; van Liefland, Marck; White, Steve; Faulds, Matthew; Harris, Meredyth; Kelly, Carrie; Nicol, Scott; Pearson, Sally Anne; Chukkambotla, Srikanth; Andrew, Alyson; Attrill, Elizabeth; Campbell, Graham; Datson, Amanda; Fouracres, Anna; Graterol, Juan; Graves, Lynne; Hong, Bosun; Ishimaru, Alexander; Karthikeyan, Arvind; King, Helen; Lawson, Tom; Lee, Gregory; Lyons, Saoirse; Hall, Andrew Macalister; Mathoulin, Sophie; Mcintyre, Eilidh; Mclaughlin, Danny; Mulcahy, Kathleen; Paddle, Jonathan; Ratcliffe, Anna; Robbins, James; Sung, Weilin; Tayo, Adeoluwa; Trembath, Lisa; Venugopal, Suneetha; Walker, Robert; Wigmore, Geoffrey; Boereboom, Catherine; Downes, Charlotte; Humphries, Ryan; Melbourne, Susan; Smith, Coral; Tou, Samson; Ullah, Shafa; Batchelor, Nick; Boxall, Leigh; Broomby, Rupert; Deen, Tariq; Hellewell, Alistair; Helliwell, Laurence; Hutchings, Melanie; Hutchins, David; Keenan, Samantha; Mackie, Donna; Potter, Alison; Smith, Frances; Stone, Lucy; Thorpe, Kevin; Wassall, Richard; Woodgate, Andrew; Baillie, Shelley; Campbell, Tara; James, Sarah; King, Chris; Marques de Araujo, Daniela; Martin, Daniel; Morkane, Clare; Neely, Julia; Rajendram, Rajkumar; Burton, Megan; James, Kathryn; Keevil, Edward; Minik, Orsolya; Morgan, Jenna; Musgrave, Anna; Rajanna, Harish; Roberts, Tracey; Adamson, Michael; Jumbe, Sandra; Kendall, Jennie; Muthuswamy, Mohan Babu; Anderson, Charlotte; Cruikshanks, Andrew; Wrench, Ian; Zeidan, Lisa; Ardern, Diane; Harris, Benjamin; Hellstrom, Johanna; Martin, Jane; Thomas, Richard; Varsani, Nimu; Brown, Caroline Wrey; Docherty, Philip; Gillies, Michael; McGregor, Euan; Usher, Helen; Craig, Jayne; Smith, Andrew; Ahmad, Tahania; Bodger, Phoebe; Creary, Thais; Fowler, Alexander; Hewson, Russ; Ijuo, Eke; Jones, Timothy; Kantsedikas, Ilya; Lahiri, Sumitra; McLean, Aaron Lawson; Niebrzegowska, Edyta; Phull, Mandeep; Wang, Difei; Wickboldt, Nadine; Baldwin, Jacqueline; Doyle, Donna; Mcmullan, Sean; Oladapo, Michelle; Owen, Thomas; Williams, Alexandra; Daniel, Hull; Gregory, Peter; Husain, Tauqeer; Kirk-Bayley, Justin; Mathers, Edward; Montague, Laura; Harper, Mark; White, Stuart; Jack, James; Ridley, Carrie; Avis, Joanne; Cook, Tim; Dali-Kemmery, Lola; Kerslake, Ian; Lambourne, Victoria; Pearson, Annabel; Boyd, Christine; Callaghan, Mark; Lawson, Cathy; McCrossan, Roopa; Nesbitt, Vanessa; O'connor, Laura; Scott, Julia; Sinclair, Rhona; Farid, Nahla; Morgese, Ciro; Bhatia, Kailash; Karmarkar, Swati; Ahmed, Jamil; Branagan, Graham; Hutton, Monica; Swain, Andrew; Brookes, Jamie; Cornell, Jonathan; Dolan, Rachael; Hulme, Jonathan; Jansen van Vuuren, Amanda; Jowitt, Tom; Kalashetty, Gunasheela; Lloyd, Fran; Patel, Kiran; Sherwood, Nicholas; Brown, Lynne; Chandler, Ben; Deighton, Kerry; Emma, Temlett; Haunch, Kirsty; Cheeseman, Michelle; Dent, Kathy; Garg, Sanjeev; Gray, Carol; Hood, Marion; Jones, Dawn; Juj, Joanne; Rao, Roshan; Walker, Tara; Al Anizi, Mashel; Cheah, Clarissa; Cheing, Yushio; Coutinho, Francisco; Gondo, Prisca; Hadebe, Bernard; Hove, Mazvangu Onie; Khader, Ahamed; Krishnachetty, Bobby; Rhodes, Karen; Sokhi, Jagdish; Baker, Katie-Anne; Bertram, Wendy; Looseley, Alex; Mouton, Ronelle; Hanna, George; Arnold, Glenn; Arya, Shobhit; Balfoussia, Danai; Baxter, Linden; Harris, James; Jones, Craig; Knaggs, Alison; Markar, Sheraz; Perera, Anisha; Scott, Alasdair; Shida, Asako; Sirha, Ravneet; Wright, Sally; Frost, Victoria; Gray, Catherine; Andrews, Emma; Arrandale, Lindsay; Barrett, Stephen; Cifra, Elna; Cooper, Mariese; Dragnea, Dragos; Elna, Cifra; Maclean, Jennifer; Meier, Sonja; Milliken, Donald; Munns, Christopher; Ratanshi, Nadir; Ramessur, Suneil; Salvana, Abegail; Watson, Anthony; Ali, Hani; Campbell, Gill; Critchley, Rebecca; Endersby, Simon; Hicks, Catherine; Liddle, Alison; Pass, Marc; Ritchie, Charlotte; Thomas, Charlotte; Too, Lingxi; Welsh, Sarah; Gill, Talvinder; Johnson, Joanne; Reed, Joanne; Davis, Edward; Papadopoullos, Sam; Attwood, Clare; Biffen, Andrew; Boulton, Kerenza; Gray, Sophie; Hay, David; Mills, Sarah; Montgomery, Jane; Riddell, Rory; Simpson, James; Bhardwaj, Neeraj; Paul, Elaine; Uwubamwen, Nosakhare; Alexander, Maini; Arrich, James; Arumugam, Swarna; Blackwood, Douglas; Boggiano, Victoria; Brown, Robyn; Chan, Yik Lam; Chatterjee, Devnandan; Chhabra, Ashok; Christian, Rachel; Costelloe, Hannah; Matthewman, Madeline Coxwell; Dalton, Emma; Darko, Julia; Davari, Maria; Dave, Tejal; Deacon, Matthew; Deepak, Shantal; Edmond, Holly; Ellis, Jessica; El-Sayed, Ahmed; Eneje, Philip; English, Rose; Ewe, Renee; Foers, William; Franklin, John; Gallego, Laura; Garrett, Emily; Goldberg, Olivia; Goss, Harry; Greaves, Rosanna; Harris, Rudy; Hennings, Charles; Jones, Eleanor; Kamali, Nelson; Kokkinos, Naomi; Lewis, Carys; Lignos, Leda; Malgapo, Evaleen Victoria; Malik, Rizwana; Milne, Andrew; Mulligan, John-Patrick; Nicklin, Philippa; Palipane, Natasha; Parsons, Thomas; Piper, Rebecca; Prakash, Rohan; Ramesh, Byron; Rasip, Sarah; Reading, Jacob; Rela, Mariam; Reyes, Anna; Stephens, Robert; Rooms, Martin; Shah, Karishma; Simons, Henry; Solanki, Shalil; Spowart, Emma; Stevens, Amy; Thomas, Christopher; Waggett, Helena; Yassaee, Arrash; Kennedy, Anthony; Scott, Sara; Somanath, Sameer; Berg, Andrew; Hernandez, Miguel; Nanda, Rajesh; Tank, Ghanshyambhai; Wilson, Natalie; Wilson, Debbie; Al-Soudaine, Yassr; Baldwin, Matthew; Cornish, Julie; Davies, Zoe; Davies, Leigh; Edwards, Marc; Frewer, Natasha; Gallard, Sian; Glasbey, James; Harries, Rhiannon; Hopkins, Luke; Kim, Taeyang; Koompirochana, Vilavan; Lawson, Simon; Lewis, Megan; Makzal, Zaid; Scourfield, Sarah; Ahmad, Yousra; Bates, Sarah; Blackwell, Clare; Bryant, Helen; Collins, Hannah; Coulter, Suzanne; Cruickshank, Ross; Daniel, Sonya; Daubeny, Thomas; Edwards, Mark; Golder, Kim; Hawkins, Lesley; Helen, Bryant; Hinxman, Honor; Levett, Denny; Salmon, Karen; Seaward, Leanne; Skinner, Ben; Tyrell, Bryony; Wadams, Beverley; Walsgrove, Joseph; Dickson, Jane; Constantin, Kathryn; Karen, Markwell; O'Brien, Peter; O'Donohoe, Lynn; Payne, Hannah; Sundayi, Saul; Walker, Elaine; Brooke, Jenny; Cardy, Jon; Humphreys, Sally; Kessack, Laura; Kubitzek, Christiane; Kumar, Suhas; Cotterill, Donna; Hodzovic, Emil; Hosdurga, Gurunath; Miles, Edward; Saunders, Glenn; Campbell, Marta; Chan, Peter; Jemmett, Kim; Raj, Ashok; Naik, Aditi; Oshowo, Ayo; Ramamoorthy, Rajarajan; Shah, Nimesh; Sylvan, Axel; Blyth, Katharine; Burtenshaw, Andrew; Freeman, David; Johnson, Emily; Lo, Philip; Martin, Terry; Plunkett, Emma; Wollaston, Julie; Allison, Joanna; Carroll, Christine; Craw, Nicholas; Craw, Sarah; Pitt-Kerby, Tressy; Rowland-Axe, Rebecca; Spurdle, Katie; McDonald, Andrew; Simon, Davies; Sinha, Vivek; Smith, Thomas; Banner-Goodspeed, Valerie; Boone, Myles; Campbell, Kathleen; Lu, Fengxin; Scannell, Joseph; Sobol, Julia; Balajonda, Naraida; Clemmons, Karen; Conde, Carlos; Elgasim, Magdi; Funk, Bonita; Hall, Roger; Hopkins, Thomas; Olaleye, Omowunmi; Omer, Omer; Pender, Michelle; Porto, Angelo; Stevens, Alice; Waweru, Peter; Yeh, Erlinda; Bodansky, Daniella; Evans, Adam; Kleopoulos, Steven; Maril, Robert; Mathney, Edward; Sanchez, Angela; Tinuoye, Elizabeth; Bateman, Brian; Eng, Kristen; Jiang, Ning; Ladha, Karim; Needleman, Joseph; Chen, Lee-Lynn; Lane, Rondall; Robinowitz, David; Ghushe, Neil; Irshad, Mariam; O'Connor, John; Patel, Samir; Takemoto, Steven; Wallace, Art; Mazzeffi, Michael; Rock, Peter; Wallace, Karin; Zhu, Xiaomao; Chua, Pandora; Mattera, Matthew; Sharar, Rebecca; Thilen, Stephan; Treggiari, Miriam; Morgan, Angela; Sofjan, Iwan; Subramaniam, Kathirvel; Avidan, Michael; Maybrier, Hannah; Muench, Maxwell; Wildes, Troy

    2018-01-01

    The surgical safety checklist is widely used to improve the quality of perioperative care. However, clinicians continue to debate the clinical effectiveness of this tool. Prospective analysis of data from the International Surgical Outcomes Study (ISOS), an international observational study of

  7. Topic A. Have all the relevant issues been identified

    International Nuclear Information System (INIS)

    Bernero, R.M.

    1994-01-01

    This work is an answer to the question : have all the relevant issues been identified? The author tries to answer more particularly to the following three points : 1) can risk or responsibility for action be imposed on future generations. 2) Are current safety norms suitable for the future? 3) what controls are appropriate for inter generational cost/benefit evaluations. (O.L.)

  8. Social signals of safety and risk confer utility and have asymmetric effects on observers' choices.

    Science.gov (United States)

    Chung, Dongil; Christopoulos, George I; King-Casas, Brooks; Ball, Sheryl B; Chiu, Pearl H

    2015-06-01

    Individuals' risk attitudes are known to guide choices about uncertain options. However, in the presence of others' decisions, these choices can be swayed and manifest as riskier or safer behavior than one would express alone. To test the mechanisms underlying effective social 'nudges' in human decision-making, we used functional neuroimaging and a task in which participants made choices about gambles alone and after observing others' selections. Against three alternative explanations, we found that observing others' choices of gambles increased the subjective value (utility) of those gambles for the observer. This 'other-conferred utility' was encoded in ventromedial prefrontal cortex, and these neural signals predicted conformity. We further identified a parametric interaction with individual risk preferences in anterior cingulate cortex and insula. These data provide a neuromechanistic account of how information from others is integrated with individual preferences that may explain preference-congruent susceptibility to social signals of safety and risk.

  9. Safety guide on fire protection in nuclear power plants

    International Nuclear Information System (INIS)

    1976-01-01

    The purpose of the Safety Guide is to give specific design and operational guidance for protection from fire and explosion in nuclear power plants, based on the general guidance given in the relevant sections of the 'Safety Code of Practice - Design' and the 'Safety Code of Practice - Operation' of the International Atomic Energy Agency. The guide will confine itself to fire protection of safety systems and items important to safety, leaving the non-safety matters of fire protection in nuclear power plants to be decided upon the basis of the various available national and international practices and regulations. (HP) [de

  10. Food safety ontology and text mining strategies as a tool in (re)emerging risk identification

    NARCIS (Netherlands)

    Brug, F. van de

    2009-01-01

    Industry and government are held responsible for the safety of food and feed products. Therefore actual and relevant information concerning emerging safety risks is crucial. But how is it possible to filter relevant information from the fast growing volumes of information produced by science and the

  11. Safety and Effectiveness of Vibration Massage by Deep Oscillations: A Prospective Observational Study

    Directory of Open Access Journals (Sweden)

    Karin Kraft

    2013-01-01

    Full Text Available The objective of this study is to assess the safety of treatment with vibration massage using a deep oscillation device and the effects on symptom severity and quality of life in patients with primary fibromyalgia syndrome (FMS. Outpatients with FMS performed an observational prospective study with visits 2–4 weeks after the last treatment (control and after further 2 months (follow-up. Patients were treated with 10 sessions of 45 min deep oscillation massage, 2/week. Primary outcome parameters were safety and tolerability (5-level Likert scale (1 = very good (after each treatment session and at control visit. Secondary outcome parameters were symptom severity (Fibromyalgia Impact Questionnaire (FIQ, pain and quality of life (SF-36. Seventy patients (97.1% females were included. At control visit, 41 patients (58.6% reported 63 mild and short-lasting adverse events, mainly worsening of prevalent symptoms such as pain and fatigue. Tolerability was rated as 1.8 (95% confidence interval: 1.53; 2.07. Symptoms and quality of life were significantly improved at both control and follow-up visits (at least P<0.01. In conclusion, deep oscillation massage is safe and well tolerated in patients with FMS and might improve symptoms and quality of life rather sustained.

  12. Wanted! Possible links between religious coping and safety

    DEFF Research Database (Denmark)

    Knudsen, Fabienne; Grøn, Sisse

    . The injuries, though, are not evenly distributed and seem to depend on a range of factors, of which the type of ship and the nationality of the seafarer are critical. Statistics show that Filipino seafarers working on Danish ships have less than 50% reported accidents compared to Danes - the Danes having...... lower risk of occupational accidents than seafarers from Western Europe. Therefore, the project will seek to identify relevant aspects of both reporting practice and safety culture in Danish seafaring.   The objective of the project is to identify causes behind the registered difference in numbers...... of injuries among Danish seafarers and their foreign colleagues, in order to direct future safety initiative towards the relevant factors. The research questions are as follows: How is safety learnt, conceived of, communicated and practiced, within the national groupings, and between the national groupings...

  13. Proceedings of the Nuclear Criticality Technology Safety Workshop

    Energy Technology Data Exchange (ETDEWEB)

    Rene G. Sanchez

    1998-04-01

    This document contains summaries of most of the papers presented at the 1995 Nuclear Criticality Technology Safety Project (NCTSP) meeting, which was held May 16 and 17 at San Diego, Ca. The meeting was broken up into seven sessions, which covered the following topics: (1) Criticality Safety of Project Sapphire; (2) Relevant Experiments For Criticality Safety; (3) Interactions with the Former Soviet Union; (4) Misapplications and Limitations of Monte Carlo Methods Directed Toward Criticality Safety Analyses; (5) Monte Carlo Vulnerabilities of Execution and Interpretation; (6) Monte Carlo Vulnerabilities of Representation; and (7) Benchmark Comparisons.

  14. Health and safety at DNE [Dounreay Nuclear Power Development Establishment

    International Nuclear Information System (INIS)

    Walford, J.G.; Tyler, G.R.

    1988-11-01

    This report reviews health and safety experience at the UKAEA's Dounreay Nuclear Power Development Establishment for 1986 and gives relevant data in the fields of health physics and general safety. It includes sections on: organization, policy and training; monitoring of the working environment; personnel monitoring; protection of the public; radiological incidents; and non-radiological health and safety. (author)

  15. Safety implications of electronic driving support systems : an orientation.

    NARCIS (Netherlands)

    Gundy, C.M. Steyvers, F.J.J.M. & Kaptein, N.A.

    1995-01-01

    This report focuses on traffic safety aspects of driving support systems. The report consists of two parts. First of all, the report discusses a number of topics, relevant for the implementation and evaluation of driving support systems. These topics include: (1) safety research into driving support

  16. Consideration of social scientific issues in a safety case. Final report

    International Nuclear Information System (INIS)

    Sailer, Michael; Kallenbach-Herbert, Beate; Brohmann, Bettina; Spieth-Achtnich, Angelika

    2010-01-01

    The research outcome presented here - a model for identifying and describing safety-relevant social scientific issues - provides a scientific basis for addressing these issues in a safety case. In order for them to be implemented in a repository process, it would be necessary to elaborate in greater detail the initial conceptual foundations that have been laid in this research project in line with the project's terms of reference. The requisite elaboration relates to binding rules for designing the repository process, particularly with regard to the stages in which the safety case is to be developed during planning, approval, construction and operation through to repository closure. Such detailed elaboration also needs to involve specifying the extent to which each social scientific issue and sub-issue is to be addressed in the different stages. Consideration would need to be given not only to the relevance of the issue for a given stage but also to the various options and methods for providing proof of safety. It would be possible to draw on experiences with handling safety management in nuclear power plants - a sphere in which over the last ten years efforts have been ongoing to develop methods for presentation by the operator and review by the authorities. Furthermore, it is likely that the social scientific issues relevant to a safety case cannot be defined once and for all in a single process, but that the need for continual revision and adaptation will arise due to both the increasing knowledge acquired during the course of the repository process and the experiences and expectations of stakeholders (similarly to experiences in the sphere of scientific-technological requirements). Appropriate conditions need to be defined for such a process. This process could be supported by implementing the option mentioned above whereby a regulatory definition of safety management for geological disposal is formulated which encompasses all safety-relevant social scientific

  17. An Overview of INEL Fusion Safety R&D Facilities

    Science.gov (United States)

    McCarthy, K. A.; Smolik, G. R.; Anderl, R. A.; Carmack, W. J.; Longhurst, G. R.

    1997-06-01

    The Fusion Safety Program at the Idaho National Engineering Laboratory has the lead for fusion safety work in the United States. Over the years, we have developed several experimental facilities to provide data for fusion reactor safety analyses. We now have four major experimental facilities that provide data for use in safety assessments. The Steam-Reactivity Measurement System measures hydrogen generation rates and tritium mobilization rates in high-temperature (up to 1200°C) fusion relevant materials exposed to steam. The Volatilization of Activation Product Oxides Reactor Facility provides information on mobilization and transport and chemical reactivity of fusion relevant materials at high temperature (up to 1200°C) in an oxidizing environment (air or steam). The Fusion Aerosol Source Test Facility is a scaled-up version of VAPOR. The ion-implanta-tion/thermal-desorption system is dedicated to research into processes and phenomena associated with the interaction of hydrogen isotopes with fusion materials. In this paper we describe the capabilities of these facilities.

  18. Structural observation of long-span suspension bridges for safety assessment: implementation of an optical displacement measurement system

    International Nuclear Information System (INIS)

    Martins, L Lages; Ribeiro, A Silva; Rebordão, J M

    2015-01-01

    This paper addresses the implementation of an optical displacement measurement system in the observation scenario of a long-span suspension bridge and its contribution for structural safety assessment. The metrological background required for quality assurance of the measurements is described, namely, the system's intrinsic parameterization and integration in the SI dimensional traceability chain by calibration, including its measurement uncertainty assessment

  19. Interface for safety and security of radioactive sources

    International Nuclear Information System (INIS)

    Seggane, Richard

    2016-04-01

    In facilities and activities involving use of radiation sources, safety and security measures have in common the aim of protecting human life and health and the environment. In addition, safety and security measures must be designed and implemented in an integrated manner, so that security measures do not compromise safety and safety measures do not compromise security measures. This work reviewed issues related to establishing a clear interface between safety and security of radiation sources. The Government, the Regulatory Authority and licensee/registrants and other relevant stakeholders should work together and contribute to ensure that safety and security of sources is ensured and well interfaced. A Radiotherapy facility has been used as a case study. (au)

  20. Canadian contributions to the safety and environmental aspects of fusion

    International Nuclear Information System (INIS)

    Stasko, R.; Wong, K.

    1987-05-01

    Since next-step fusion devices will be fuelled with mixtures of tritium and deuterium, the knowledge base and tritium handling experience associated with the operation of CANDU reactors is viewed as relevant to the development of safe fusion technology. Fusion safety issues will be compared with fission safety experience, after which specific Canadian activities in support of fusion safety will be overviewed. In addition, recommendations for appropriate fusion safety criteria will be summarized. 18 refs

  1. Healthcare professionals’ views of feedback on patient safety culture assessment.

    OpenAIRE

    Zwijnenberg, N.C.; Hendriks, M.; Hoogervorst-Schilp, J.; Wagner, C.

    2016-01-01

    Background: By assessing patient safety culture, healthcare providers can identify areas for improvement in patient safety culture. To achieve this, these assessment outcomes have to be relevant and presented clearly. The aim of our study was to explore healthcare professionals’ views on the feedback of a patient safety culture assessment. Methods: Twenty four hospitals participated in a patient safety culture assessment in 2012. Hospital departments received feedback in a report and on a web...

  2. Guidelines for the Review of Research Reactor Safety: Revised Edition. Reference Document for IAEA Integrated Safety Assessment of Research Reactors (INSARR)

    International Nuclear Information System (INIS)

    2013-01-01

    The Integrated Safety Assessment of Research Reactors (INSARR) is an IAEA safety review service available to Member States with the objective of supporting them in ensuring and enhancing the safety of their research reactors. This service consists of performing a comprehensive peer review and an assessment of the safety of the respective research reactor. The reviews are based on IAEA safety standards and on the provisions of the Code of Conduct on the Safety of Research Reactors. The INSARR can benefit both the operating organizations and the regulatory bodies of the requesting Member States, and can include new research reactors under design or operating research reactors, including those which are under a Project and Supply Agreement with the IAEA. The first IAEA safety evaluation of a research reactor operated by a Member State was completed in October 1959 and involved the Swiss 20 MW DIORIT research reactor. Since then, and in accordance with its programme on research reactor safety, the IAEA has conducted safety review missions in its Member States to enhance the safety of their research reactor facilities through the application of the Code of Conduct on the Safety of Research Reactors and the relevant IAEA safety standards. About 320 missions in 51 Member States were undertaken between 1972 and 2012. The INSARR missions and other limited scope safety review missions are conducted following the guidelines presented in this publication, which is a revision of Guidelines for the Review of Research Reactor Safety (IAEA Services Series No. 1), published in December 1997. This publication details those IAEA safety standards and guidance publications relevant to the safety of research reactors that have been revised or published since 1997. The purpose of this publication is to give guidance on the preparation, implementation, reporting and follow-up of safety review missions. It is also intended to be of assistance to operators and regulators in conducting

  3. Complex mixtures: Relevance of combined exposure to substances at low dose levels

    NARCIS (Netherlands)

    Leeman, W.R.; Krul, L.; Houben, G.F.

    2013-01-01

    Upon analysis of chemically complex food matrices a forest of peaks is likely to be found. Identification of these peaks and concurrent determination of the toxicological relevance upon exposure is very time consuming, expensive and often requires animal studies. Recently, a safety assessment

  4. Safety and environmental impacts

    International Nuclear Information System (INIS)

    Fiege, A.; Kramer, W.

    1991-01-01

    By means of interpreting experimental results, and by means of conservative estimates, several fundamental statements can be made concerning the safety and environmental impacts of fusion plants. Relevant findings so far regarding normal operation and incidents as well as risks involved in raw material extraction and waste management are compiled. (DG) [de

  5. The Health and Safety Executive's regulatory framework for control of nuclear criticality safety

    International Nuclear Information System (INIS)

    Smith, K.; Simister, D.N.

    1991-01-01

    In the United Kingdom the Health and Safety at Work Act, 1974 is the main legal instrument under which risks to people from work activities are controlled. Certain sections of the Nuclear Installations Act, 1965 which deal with the licensing of nuclear sites and the regulatory control of risks arising from them, including the risk from accidental criticality, are relevant statutory provisions of the Health and Safety at Work Act. The responsibility for safety rests with the operator who has to make and implement arrangements to prevent accidental criticality. The adequacy of these arrangements must be demonstrated in a safety case to the regulatory authorities. Operators are encouraged to treat each plant on its own merits and develop the safety case accordingly. The Nuclear Installations Inspectorate (NII), for its part, assesses the adequacy of the operator's safety case against the industry's own standards and criteria, but more particularly against the NII's safety assessment principles and guides, and international standards. Risks should be made as low as reasonably practicable. Generally, the NII seeks improvements in safety using an enforcement policy which operates at a number of levels, ranging from persuasion through discussion to the ultimate deterrent of withdrawal of a site licence. This paper describes the role of the NII, which includes a specialist criticality expertise, within the Health and Safety Executive, in regulating the nuclear sites from the criticality safety viewpoint. (Author)

  6. Healthcare professionals’ views of feedback on patient safety culture assessment.

    NARCIS (Netherlands)

    Zwijnenberg, N.C.; Hendriks, M.; Hoogervorst-Schilp, J.; Wagner, C.

    2016-01-01

    Background: By assessing patient safety culture, healthcare providers can identify areas for improvement in patient safety culture. To achieve this, these assessment outcomes have to be relevant and presented clearly. The aim of our study was to explore healthcare professionals’ views on the

  7. Safety-relevant hydrogeological properties of the claystone barrier of a Swiss radioactive waste repository: An evaluation using multiple lines of evidence

    Science.gov (United States)

    Gautschi, Andreas

    2017-09-01

    In Switzerland, the Opalinus Clay - a Jurassic (Aalenian) claystone formation - has been proposed as the first-priority host rock for a deep geological repository for both low- and intermediate-level and high-level radioactive wastes. An extensive site and host rock investigation programme has been carried out during the past 30 years in Northern Switzerland, comprising extensive 2D and 3D seismic surveys, a series of deep boreholes within and around potential geological siting regions, experiments in the international Mont Terri Rock Laboratory, compilations of data from Opalinus Clay in railway and motorway tunnels and comparisons with similar rocks. The hydrogeological properties of the Opalinus Clay that are relevant from the viewpoint of long-term safety are described and illustrated. The main conclusions are supported by multiple lines of evidence, demonstrating consistency of conclusions based on hydraulic properties, porewater chemistry, distribution of natural tracers across the Opalinus Clay as well as small- and large-scale diffusion models and the derived conceptual understanding of solute transport.

  8. Safety and effectiveness of eribulin in Japanese patients with locally advanced or metastatic breast cancer: a post-marketing observational study.

    Science.gov (United States)

    Watanabe, Junichiro; Ito, Yoshinori; Ohsumi, Shozo; Mizutani, Mitsuhiro; Tashiro, Hideya; Sakurai, Kenichi; Takahashi, Masato; Saito, Tsuyoshi; Tsurutani, Junji; Mukai, Hirofumi; Yoshinami, Tetsuhiro; Takao, Shintaro; Yamamoto, Yasuhisa; Matsuoka, Toshiyuki; Iwase, Hirotaka; Iwata, Hiroji; Nakamura, Seigo; Saeki, Toshiaki

    2017-12-01

    Background This large-scale study was conducted to evaluate the safety and effectiveness of eribulin for the treatment of inoperable or recurrent breast cancer in real-world settings in Japan. Methods Between July and December 2011, eligible patients with inoperable or recurrent breast cancer receiving eribulin for the first time were centrally registered and observed for 1 year. Eribulin was administered intravenously (1.4 mg/m 2 ) on days 1 and 8 of every 3-week cycle. The primary endpoint was the frequency and intensity of adverse drug reactions (ADRs). Secondary endpoints included overall response rate (ORR) and time to treatment failure (TTF). Results Of 968 patients registered at 325 institutions, 951 and 671 were included in the safety and effectiveness analyses, respectively. In the safety population, ADRs were observed in 841 patients (88.4%). The most common (≥15% incidence) were neutropenia (66.6%), leukopenia (62.4%), lymphopenia (18.4%), and peripheral neuropathy (16.8%). The most common grade ≥ 3 ADRs (>5% incidence) were neutropenia (59.8%), leukopenia (50.5%), lymphopenia (16.1%), and febrile neutropenia (7.7%). In the effectiveness population, ORR was 16.5% (95% confidence interval: 13.7, 19.4). The median TTF was 127 days (95% confidence interval: 120, 134). Conclusions The safety and effectiveness profile of eribulin was consistent with prior studies. Eribulin had a favorable risk-benefit balance when used in real-world clinical settings.

  9. EDRP public local inquiry, UKAEA/BNFL precognition on: Aspects of Dounreay safety and local liaison relevant to EDRP

    International Nuclear Information System (INIS)

    Blumfield, C.W.

    1986-01-01

    Aspects of safety at Dounreay Nuclear Establishment, including legislation, design safety, industrial safety and radiation monitoring procedures, are discussed. The arrangements for action in an emergency are outlined. Liaison between DNE and the local community, formal and informal, is summarised. (U.K.)

  10. Chemical process safety at fuel cycle facilities

    International Nuclear Information System (INIS)

    Ayres, D.A.

    1997-08-01

    This NUREG provides broad guidance on chemical safety issues relevant to fuel cycle facilities. It describes an approach acceptable to the NRC staff, with examples that are not exhaustive, for addressing chemical process safety in the safe storage, handling, and processing of licensed nuclear material. It expounds to license holders and applicants a general philosophy of the role of chemical process safety with respect to NRC-licensed materials; sets forth the basic information needed to properly evaluate chemical process safety; and describes plausible methods of identifying and evaluating chemical hazards and assessing the adequacy of the chemical safety of the proposed equipment and facilities. Examples of equipment and methods commonly used to prevent and/or mitigate the consequences of chemical incidents are discussed in this document

  11. Nonclinical safety of the sodium-glucose cotransporter 2 inhibitor empagliflozin.

    Science.gov (United States)

    Bogdanffy, Matthew S; Stachlewitz, Robert F; van Tongeren, Susan; Knight, Brian; Sharp, Dale E; Ku, Warren; Hart, Susan Emeigh; Blanchard, Kerry

    2014-01-01

    Empagliflozin, a selective inhibitor of the renal tubular sodium-glucose cotransporter 2, was developed for treatment of type 2 diabetes mellitus. Nonclinical safety of empagliflozin was studied in a battery of tests to support global market authorization. Safety pharmacology studies indicated no effect of empagliflozin on measures of respiratory or central nervous system function in rats or cardiovascular safety in telemeterized dogs. In CD-1 mouse, Wistar Han rat, or beagle dogs up to 13, 26, or 52 weeks of treatment, respectively, empagliflozin exhibited a toxicity profile consistent with secondary supratherapeutic pharmacology related to glucose loss and included decreased body weight and body fat, increased food consumption, diarrhea, dehydration, decreased serum glucose and increases in other serum parameters reflective of increased protein catabolism, gluconeogenesis, and electrolyte imbalances, and urinary changes such as polyuria and glucosuria. Microscopic changes were consistently observed in kidney and included tubular nephropathy and interstitial nephritis (dog), renal mineralization (rat) and tubular epithelial cell karyomegaly, single cell necrosis, cystic hyperplasia, and hypertrophy (mouse). Empagliflozin was not genotoxic. Empagliflozin was not carcinogenic in female mice or female rats. Renal adenoma and carcinoma were induced in male mice only at exposures 45 times the maximum clinical dose. These tumors were associated with a spectrum of nonneoplastic changes suggestive of a nongenotoxic, cytotoxic, and cellular proliferation-driven mechanism. In male rats, testicular interstitial cell tumors and hemangiomas of the mesenteric lymph node were observed; both tumors are common in rats and are unlikely to be relevant to humans. These studies demonstrate the nonclinical safety of empagliflozin. © The Author(s) 2014.

  12. Nuclear Safety Review 2013

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-07-15

    The Nuclear Safety Review 2013 focuses on the dominant nuclear safety trends, issues and challenges in 2012. The Executive Overview provides crosscutting and worldwide nuclear safety information along with a summary of the major sections covered in this report. Sections A-E of this report cover improving radiation, transport and waste safety; strengthening safety in nuclear installations; improving regulatory infrastructure and effectiveness; enhancing emergency preparedness and response (EPR); and civil liability for nuclear damage. The Appendix provides details on the activities of the Commission on Safety Standards (CSS), and activities relevant to the IAEA Safety Standards. The world nuclear community has made noteworthy progress in strengthening nuclear safety in 2012, as promoted by the IAEA Action Plan on Nuclear Safety (hereinafter referred to as ''the Action Plan''). For example, an overwhelming majority of Member States with operating nuclear power plants (NPPs) have undertaken and essentially completed comprehensive safety reassessments ('stress tests') with the aim of evaluating the design and safety aspects of plant robustness to protect against extreme events, including: defence in depth, safety margins, cliff edge effects, multiple failures, and the prolonged loss of support systems. As a result, many have introduced additional safety measures including mitigation of station blackout. Moreover, the IAEA's peer review services and safety standards have been reviewed and strengthened where needed. Capacity building programmes have been built or improved, and EPR programmes have also been reviewed and improved. Furthermore, in 2012, the IAEA continued to share lessons learned from the Fukushima Daiichi accident with the nuclear community including through three international experts' meetings (IEMs) on reactor and spent fuel safety, communication in the event of a nuclear or radiological emergency, and protection against extreme earthquakes and tsunamis.

  13. Nuclear Safety Review 2013

    International Nuclear Information System (INIS)

    2013-07-01

    The Nuclear Safety Review 2013 focuses on the dominant nuclear safety trends, issues and challenges in 2012. The Executive Overview provides crosscutting and worldwide nuclear safety information along with a summary of the major sections covered in this report. Sections A-E of this report cover improving radiation, transport and waste safety; strengthening safety in nuclear installations; improving regulatory infrastructure and effectiveness; enhancing emergency preparedness and response (EPR); and civil liability for nuclear damage. The Appendix provides details on the activities of the Commission on Safety Standards (CSS), and activities relevant to the IAEA Safety Standards. The world nuclear community has made noteworthy progress in strengthening nuclear safety in 2012, as promoted by the IAEA Action Plan on Nuclear Safety (hereinafter referred to as ''the Action Plan''). For example, an overwhelming majority of Member States with operating nuclear power plants (NPPs) have undertaken and essentially completed comprehensive safety reassessments ('stress tests') with the aim of evaluating the design and safety aspects of plant robustness to protect against extreme events, including: defence in depth, safety margins, cliff edge effects, multiple failures, and the prolonged loss of support systems. As a result, many have introduced additional safety measures including mitigation of station blackout. Moreover, the IAEA's peer review services and safety standards have been reviewed and strengthened where needed. Capacity building programmes have been built or improved, and EPR programmes have also been reviewed and improved. Furthermore, in 2012, the IAEA continued to share lessons learned from the Fukushima Daiichi accident with the nuclear community including through three international experts' meetings (IEMs) on reactor and spent fuel safety, communication in the event of a nuclear or radiological emergency, and protection against extreme earthquakes and tsunamis

  14. Middle East food safety perspectives.

    Science.gov (United States)

    Idriss, Atef W; El-Habbab, Mohammad S

    2014-08-01

    Food safety and quality assurance are increasingly a major issue with the globalisation of agricultural trade, on the one hand, and intensification of agriculture, on the other. Consumer protection has become a priority in policy-making amongst the large economies of the Middle East and North Africa (MENA) countries following a number of food safety incidents. To enhance food safety, it is necessary to establish markets underpinned by knowledge and resources, including analysis of international rejections of food products from MENA countries, international laboratory accreditation, improved reporting systems and traceability, continued development and validation of analytical methods, and more work on correlating sensory evaluation with analytical results. MENA countries should develop a national strategy for food safety based on a holistic approach that extends from farm-to-fork and involves all the relevant stakeholders. Accordingly, food safety should be a regional programme, raising awareness among policy- and decision-makers of the importance of food safety and quality for consumer protection, food trade and economic development. © 2014 Society of Chemical Industry.

  15. Time series analysis in road safety research uisng state space methods

    OpenAIRE

    BIJLEVELD, FD

    2008-01-01

    In this thesis we present a comprehensive study into novel time series models for aggregated road safety data. The models are mainly intended for analysis of indicators relevant to road safety, with a particular focus on how to measure these factors. Such developments may need to be related to or explained by external influences. It is also possible to make forecasts using the models. Relevant indicators include the number of persons killed permonth or year. These statistics are closely watch...

  16. Failure rate data for fusion safety and risk assessment

    International Nuclear Information System (INIS)

    Cadwallader, L.C.

    1993-01-01

    The Fusion Safety Program (FSP) at the Idaho National Engineering Laboratory (INEL) conducts safety research in materials, chemical reactions, safety analysis, risk assessment, and in component research and development to support existing magnetic fusion experiments and also to promote safety in the design of future experiments. One of the areas of safety research is applying probabilistic risk assessment (PRA) methods to fusion experiments. To apply PRA, we need a fusion-relevant radiological dose code and a component failure rate data base. This paper describes the FSP effort to develop a failure rate data base for fusion-specific components

  17. Safety culture in a major nuclear fuel cycle facility

    International Nuclear Information System (INIS)

    Pushparaja; Abani, M.C.

    2002-01-01

    Human factor plays an important role in development of safety culture in any nuclear fuel cycle facility. This is more relevant in major nuclear facility such as a reactor or a reprocessing plant. In Indian reprocessing plants, an effective worker's training, education and certification program is in place to sensitize the worker's response to safety and safe work procedures. The methodology followed to self evaluation of safety culture and the benefits in a reprocessing plant is briefly discussed. Various indicators of safety performance and visible signs of a good safety management are also qualitatively analyzed. (author)

  18. Joint nuclear safety research projects between the US and Russian Federation International Nuclear Safety Centers

    International Nuclear Information System (INIS)

    Bougaenko, S.E.; Kraev, A.E.; Hill, D.L.; Braun, J.C.; Klickman, A.E.

    1998-01-01

    The Russian Federation Ministry for Atomic Energy (MINATOM) and the US Department of Energy (USDOE) formed international Nuclear Safety Centers in October 1995 and July 1996, respectively, to collaborate on nuclear safety research. Since January 1997, the two centers have initiated the following nine joint research projects: (1) INSC web servers and databases; (2) Material properties measurement and assessment; (3) Coupled codes: Neutronic, thermal-hydraulic, mechanical and other; (4) Severe accident management for Soviet-designed reactors; (5) Transient management and advanced control; (6) Survey of relevant nuclear safety research facilities in the Russian Federation; (8) Advanced structural analysis; and (9) Development of a nuclear safety research and development plan for MINATOM. The joint projects were selected on the basis of recommendations from two groups of experts convened by NEA and from evaluations of safety impact, cost, and deployment potential. The paper summarizes the projects, including the long-term goals, the implementing strategy and some recent accomplishments for each project

  19. RADWASS update. Radioactive Waste Safety Standards Programme

    International Nuclear Information System (INIS)

    Delattre, D.

    2000-01-01

    By the late 1980s, the issue of radioactive wastes and their management was becoming increasingly politically important. The IAEA responded by establishing a high profile family of safety standards, the Radioactive Waste Safety Standards (RADWASS). By this means, the IAEA intended to draw attention to the fact that well-established procedures for the safe management of radioactive wastes already were in place. The programme was intended to establish an ordered structure for safety documents on waste management and to ensure comprehensive coverage of all relevant subject areas. RADWASS documents are categorized under four subject areas - discharges, predisposal, disposal, and environmental restoration. The programme is overseen through a formalized review and approval mechanism that was established in 1996 for all safety standards activities. The Waste Safety Standards Committee (WASSC) is a standing body of senior regulatory officials with technical expertise in radioactive waste safety. To date, three Safety Requirements and seven Safety Guides have been issued

  20. Training courses on integrated safety assessment modelling for waste repositories

    International Nuclear Information System (INIS)

    Mallants, D.

    2007-01-01

    Near-surface or deep repositories of radioactive waste are being developed and evaluated all over the world. Also, existing repositories for low- and intermediate-level waste often need to be re-evaluated to extend their license or to obtain permission for final closure. The evaluation encompasses both a technical feasibility as well as a safety analysis. The long term safety is usually demonstrated by means of performance or safety assessment. For this purpose computer models are used that calculate the migration of radionuclides from the conditioned radioactive waste, through engineered barriers to the environment (groundwater, surface water, and biosphere). Integrated safety assessment modelling addresses all relevant radionuclide pathways from source to receptor (man), using in combination various computer codes in which the most relevant physical, chemical, mechanical, or even microbiological processes are mathematically described. SCK-CEN organizes training courses in Integrated safety assessment modelling that are intended for individuals who have either a controlling or supervising role within the national radwaste agencies or regulating authorities, or for technical experts that carry out the actual post-closure safety assessment for an existing or new repository. Courses are organised by the Department of Waste and Disposal

  1. International comparison of safety criteria applied to radwaste repositories. Safety aspects of the post-operational phase

    International Nuclear Information System (INIS)

    Baltes, B.

    1994-01-01

    There is a generally accepted system of framework safety conditions governing the construction, operation, and post-operational monitoring of radwaste repositories. Although the development of these framework conditions may vary from country to country, the resulting criteria are based on the commonly accepted system of priciples and purposes established for ultimate radioactive waste disposal. The experience accumulated by GRS in the course of the plan approval procedure for the Konrad mine site and the safety-relevant studies performed for the planned Morsleben repository clearly show demand for further development of the safety criteria. In Germany, it is especially the safety criteria and detailed requirements filling the framework safety conditions that need revision and in-depth definition, as well as comparison and harmonisation with internationally applied criteria. These activities will particularly consider the international convention on radioactive waste management currently in preparation under the auspieces of the IAEA. (orig.) [de

  2. Classification for Safety-Critical Car-Cyclist Scenarios Using Machine Learning

    NARCIS (Netherlands)

    Cara, I.; Gelder, E.D.

    2015-01-01

    The number of fatal car-cyclist accidents is increasing. Advanced Driver Assistance Systems (ADAS) can improve the safety of cyclists, but they need to be tested with realistic safety-critical car-cyclist scenarios. In order to store only relevant scenarios, an online classification algorithm is

  3. Applicability of trends in nuclear safety analysis to space nuclear power systems

    International Nuclear Information System (INIS)

    Bari, R.A.

    1992-01-01

    A survey is presented of some current trends in nuclear safety analysis that may be relevant to space nuclear power systems. This includes: lessons learned from operating power reactor safety and licensing; approaches to the safety design of advanced and novel reactors and facilities; the roles of risk assessment, extremely unlikely accidents, safety goals/targets; and risk-benefit analysis and communication

  4. Radiation safety for the emergency situation of the power plant accident. Radiation safety in society and its education

    International Nuclear Information System (INIS)

    Kosako, Toshiso

    2012-01-01

    Great East Japan Earthquake and Tsunamis, and following Fukushima Daiichi Nuclear Power Accident brought about great impact on society in Japan. Accident analysis of inside reactor was studied by reactor physics or reactor engineering knowledge, while dissipation of a large amount of radioactive materials outside reactor facilities, and radiation and radioactivity effects on people by way of atmosphere, water and soil were dealt with radiation safety or radiation protection. Due to extremely low frequency and experience of an emergency, there occurred a great confusion in the response of electric power company concerned, relevant regulating competent authorities, local government and media, and related scholars and researchers, which caused great anxieties amount affected residents and people. This article described radiation safety in the society and its education. Referring to actual examples, how radiation safety or radiation protection knowledge should be dealt with emergency risk management in the society was discussed as well as problem of education related with nuclear power, radiation and prevention of disaster and fostering of personnel for relevant people. (T. Tanaka)

  5. Valerian: No Evidence for Clinically Relevant Interactions

    Directory of Open Access Journals (Sweden)

    Olaf Kelber

    2014-01-01

    Full Text Available In recent popular publications as well as in widely used information websites directed to cancer patients, valerian is claimed to have a potential of adverse interactions with anticancer drugs. This questions its use as a safe replacement for, for example, benzodiazepines. A review on the interaction potential of preparations from valerian root (Valeriana officinalis L. root was therefore conducted. A data base search and search in a clinical drug interaction data base were conducted. Thereafter, a systematic assessment of publications was performed. Seven in vitro studies on six CYP 450 isoenzymes, on p-glycoprotein, and on two UGT isoenzymes were identified. However, the methodological assessment of these studies did not support their suitability for the prediction of clinically relevant interactions. In addition, clinical studies on various valerian preparations did not reveal any relevant interaction potential concerning CYP 1A2, 2D6, 2E1, and 3A4. Available animal and human pharmacodynamic studies did not verify any interaction potential. The interaction potential of valerian preparations therefore seems to be low and thereby without clinical relevance. We conclude that there is no specific evidence questioning their safety, also in cancer patients.

  6. Nuclear Safety Review for 2014

    International Nuclear Information System (INIS)

    2014-07-01

    The Nuclear Safety Review 2014 focuses on the dominant nuclear safety trends, issues and challenges in 2013. The Executive Overview provides general nuclear safety information along with a summary of the major issues covered in this report: strengthening safety in nuclear installations; improving radiation, transport and waste safety; enhancing emergency preparedness and response (EPR); improving regulatory infrastructure and effectiveness; and strengthening civil liability for nuclear damage. The Appendix provides details on the activities of the Commission on Safety Standards, and activities relevant to the Agency’s safety standards. The global nuclear community has made steady and continuous progress in strengthening nuclear safety in 2013, as promoted by the IAEA Action Plan on Nuclear Safety (hereinafter referred to as “the Action Plan”) and reported in Progress in the Implementation of the IAEA Action Plan on Nuclear Safety (document GOV/INF/2013/8-GC(57)/INF/5), and the Supplementary Information to that report and Progress in the Implementation of the IAEA Action Plan on Nuclear Safety (document GOV/INF/2014/2). • Significant progress continues to be made in several key areas, such as assessments of safety vulnerabilities of nuclear power plants (NPPs), strengthening of the Agency’s peer review services, improvements in EPR capabilities, strengthening and maintaining capacity building, and protecting people and the environment from ionizing radiation. The progress that has been made in these and other areas has contributed to the enhancement of the global nuclear safety framework. • Significant progress has also been made in reviewing the Agency’s safety standards, which continue to be widely applied by regulators, operators and the nuclear industry in general, with increased attention and focus on vitally important areas such as design and operation of NPPs, protection of NPPs against severe accidents, and EPR. • The Agency continued to

  7. Cross-comparison of three surrogate safety methods to diagnose cyclist safety problems at intersections in Norway.

    Science.gov (United States)

    Laureshyn, Aliaksei; Goede, Maartje de; Saunier, Nicolas; Fyhri, Aslak

    2017-08-01

    Relying on accident records as the main data source for studying cyclists' safety has many drawbacks, such as high degree of under-reporting, the lack of accident details and particularly of information about the interaction processes that led to the accident. It is also an ethical problem as one has to wait for accidents to happen in order to make a statement about cyclists' (un-)safety. In this perspective, the use of surrogate safety measures based on actual observations in traffic is very promising. In this study we used video data from three intersections in Norway that were all independently analysed using three methods: the Swedish traffic conflict technique (Swedish TCT), the Dutch conflict technique (DOCTOR) and the probabilistic surrogate measures of safety (PSMS) technique developed in Canada. The first two methods are based on manual detection and counting of critical events in traffic (traffic conflicts), while the third considers probabilities of multiple trajectories for each interaction and delivers a density map of potential collision points per site. Due to extensive use of microscopic data, PSMS technique relies heavily on automated tracking of the road users in video. Across the three sites, the methods show similarities or are at least "compatible" with the accident records. The two conflict techniques agree quite well for the number, type and location of conflicts, but some differences with no obvious explanation are also found. PSMS reports many more safety-relevant interactions including less severe events. The location of the potential collision points is compatible with what the conflict techniques suggest, but the possibly significant share of false alarms due to inaccurate trajectories extracted from video complicates the comparison. The tested techniques still require enhancement, with respect to better adjustment to analysis of the situations involving cyclists (and vulnerable road users in general) and further validation. However, we

  8. Legal Aspects of Radioactive Waste Management: Relevant International Legal Instruments

    International Nuclear Information System (INIS)

    Wetherall, Anthony; Robin, Isabelle

    2014-01-01

    The responsible use of nuclear technology requires the safe and environmentally sound management of radioactive waste, for which countries need to have stringent technical, administrative and legal measures in place. The legal aspects of radioactive waste management can be found in a wide variety of legally binding and non-binding international instruments. This overview focuses on the most relevant ones, in particular those on nuclear safety, security, safeguards and civil liability for nuclear damage. It also identifies relevant regional instruments concerning environmental matters, in particular, with regard to strategic environmental assessments (SEAs), environmental impact assessments (EIAs), public access to information and participation in decision-making, as well as access to justice

  9. Safety Aspects of Sustainable Storage Dams and Earthquake Safety of Existing Dams

    Directory of Open Access Journals (Sweden)

    Martin Wieland

    2016-09-01

    Full Text Available The basic element in any sustainable dam project is safety, which includes the following safety elements: ① structural safety, ② dam safety monitoring, ③ operational safety and maintenance, and ④ emergency planning. Long-term safety primarily includes the analysis of all hazards affecting the project; that is, hazards from the natural environment, hazards from the man-made environment, and project-specific and site-specific hazards. The special features of the seismic safety of dams are discussed. Large dams were the first structures to be systematically designed against earthquakes, starting in the 1930s. However, the seismic safety of older dams is unknown, as most were designed using seismic design criteria and methods of dynamic analysis that are considered obsolete today. Therefore, we need to reevaluate the seismic safety of existing dams based on current state-of-the-art practices and rehabilitate deficient dams. For large dams, a site-specific seismic hazard analysis is usually recommended. Today, large dams and the safety-relevant elements used for controlling the reservoir after a strong earthquake must be able to withstand the ground motions of a safety evaluation earthquake. The ground motion parameters can be determined either by a probabilistic or a deterministic seismic hazard analysis. During strong earthquakes, inelastic deformations may occur in a dam; therefore, the seismic analysis has to be carried out in the time domain. Furthermore, earthquakes create multiple seismic hazards for dams such as ground shaking, fault movements, mass movements, and others. The ground motions needed by the dam engineer are not real earthquake ground motions but models of the ground motion, which allow the safe design of dams. It must also be kept in mind that dam safety evaluations must be carried out several times during the long life of large storage dams. These features are discussed in this paper.

  10. Management of safety culture

    International Nuclear Information System (INIS)

    Kavsek, D.

    2004-01-01

    The strengthening of safety culture in an organization has become an increasingly important issue for nuclear industry. A high level of safety performance is essential for business success in intensely competitive global environment. This presentation offers a discussion of some principles and activities used in enhancing safety performance and appropriate safety behaviour at the Krsko NPP. Over the years a number of events have occurred in nuclear industry that have involved problems in human performance. A review of these and other significant events has identified recurring weaknesses in plant safety culture and policy. Focusing attention on the strengthening of relevant processes can help plants avoid similar undesirable events. The policy of the Krsko NPP is that all employees concerned shall constantly be alert to opportunities to reduce risks to the lowest practicable level and to achieve excellence in plant safety. The most important objective is to protect individuals, society and the environment by establishing and maintaining an effective defense against radiological hazard in the nuclear power plant. It is achieved through the use of reliable structures, components, systems, and procedures, as well as plant personnel committed to a strong safety culture. The elements of safety culture include both organizational and individual aspects. Elements commonly included at the organizational level are senior management commitment to safety, organizational effectiveness, effective communication, organizational learning, and a culture that encourages identification and resolution of safety issues. Elements identified at the individual level include personal accountability, a questioning attitude, communication, procedural adherence, etc.(author)

  11. Brief history of patient safety culture and science.

    Science.gov (United States)

    Ilan, Roy; Fowler, Robert

    2005-03-01

    The science of safety is well established in such disciplines as the automotive and aviation industry. In this brief history of safety science as it pertains to patient care, we review remote and recent publications that have guided the maturation of this field that has particular relevance to the complex structure of systems, personnel, and therapies involved in caring for the critically ill.

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

    Science.gov (United States)

    Decker, Kurt; Brinkman, Hans; Raimond, Emmanuel

    2017-04-01

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

  13. Why relevance theory is relevant for lexicography

    DEFF Research Database (Denmark)

    Bothma, Theo; Tarp, Sven

    2014-01-01

    This article starts by providing a brief summary of relevance theory in information science in relation to the function theory of lexicography, explaining the different types of relevance, viz. objective system relevance and the subjective types of relevance, i.e. topical, cognitive, situational...... that is very important for lexicography as well as for information science, viz. functional relevance. Since all lexicographic work is ultimately aimed at satisfying users’ information needs, the article then discusses why the lexicographer should take note of all these types of relevance when planning a new...... dictionary project, identifying new tasks and responsibilities of the modern lexicographer. The article furthermore discusses how relevance theory impacts on teaching dictionary culture and reference skills. By integrating insights from lexicography and information science, the article contributes to new...

  14. Efficacy and Safety of Fingolimod in an Unselected Patient Population.

    Directory of Open Access Journals (Sweden)

    Maria Rasenack

    Full Text Available Fingolimod is a first in class oral compound approved for the treatment of relapsing-remitting multiple sclerosis (RR-MS. The aim of this study was to evaluate clinical and neuroradiological responses to fingolimod as well as the safety and tolerability in RR-MS patients in clinical practice. In addition, a panel of pro-inflammatory serum cytokines was explored as potential biomarker for treatment response.We conducted a retrospective, non-randomized, open-label, observational study in 105 patients with RR-MS and measured cytokines in longitudinal serum samples.Compared to the year before fingolimod start the annualized relapse rate was reduced by 44%. Also, the percentage of patients with a worsening of the EDSS decreased. Accordingly, the fraction of patients with no evidence of disease activity (no relapse, stable EDSS, no new active lesions in MRI increased from 11% to 38%. The efficacy and safety were comparable between highly active patients or patients with relevant comorbidities and our general patient population.The efficacy in reducing relapses was comparable to that observed in the phase III trials. In our cohort fingolimod was safe and efficacious irrespective of comorbidities and previous treatment.

  15. Hydroxyethyl starch 130/0.42/6:1 for perioperative plasma volume replacement in 1130 children: results of an European prospective multicenter observational postauthorization safety study (PASS)

    NARCIS (Netherlands)

    Sümpelmann, Robert; Kretz, Franz-Josef; Luntzer, Robert; de Leeuw, Thomas G.; Mixa, Vladimir; Gäbler, Ralf; Eich, Christoph; Hollmann, Markus W.; Osthaus, Wilhelm A.

    2012-01-01

    Introduction: Third-generation hydroxyethyl starch (HES) is now approved also for the use in children, but safety studies including large numbers of pediatric patients are still missing. Therefore, we performed an European multicentric prospective observational postauthorization safety study (PASS)

  16. A generalized approach to wheat yield forecasting using earth observations: Data considerations, application and relevance

    Science.gov (United States)

    Becker-Reshef, Inbal

    In recent years there has been a dramatic increase in the demand for timely, comprehensive global agricultural intelligence. The issue of food security has rapidly risen to the top of government agendas around the world as the recent lack of food access led to unprecedented food prices, hunger, poverty, and civil conflict. Timely information on global crop production is indispensable for combating the growing stress on the world's crop production, for stabilizing food prices, developing effective agricultural policies, and for coordinating responses to regional food shortages. Earth Observations (EO) data offer a practical means for generating such information as they provide global, timely, cost-effective, and synoptic information on crop condition and distribution. Their utility for crop production forecasting has long been recognized and demonstrated across a wide range of scales and geographic regions. Nevertheless it is widely acknowledged that EO data could be better utilized within the operational monitoring systems and thus there is a critical need for research focused on developing practical robust methods for agricultural monitoring. Within this context this dissertation focused on advancing EO-based methods for crop yield forecasting and on demonstrating the potential relevance for adopting EO-based crop forecasts for providing timely reliable agricultural intelligence. This thesis made contributions to this field by developing and testing a robust EO-based method for wheat production forecasting at state to national scales using available and easily accessible data. The model was developed in Kansas (KS) using coarse resolution normalized difference vegetation index (NDVI) time series data in conjunction with out-of-season wheat masks and was directly applied in Ukraine to assess its transferability. The model estimated yields within 7% in KS and 10% in Ukraine of final estimates 6 weeks prior to harvest. The relevance of adopting such methods to

  17. Safety: Science and technique in social problems

    International Nuclear Information System (INIS)

    Smit, W.A.

    1982-01-01

    The author describes in a simple and clearly written Dutch text the relationship between scientific and technical knowledge and the social problems concerning the safety of nuclear energy. He begins with the cooling system of reactors and the safety aspects of the associated pumps. He uses this example to illustrate that the quantative determination of failure risks need not necessarily be relevant for judging the acceptance of the risk but is always relevant as a method of judging the effect of technical improvements on safety values. The author then considers the radiological effects of the operation of a nuclear plant by presenting the doses of radioactivity released if a reactor is operating normally, if there are technical problems and in the case of accidents. The corresponding biological effects on man are also presented and in an appendix the radiological consequences of reactor accidents are considered in some detail. He describes a number of models used in such calculations - for metereological distribution, dosimetry for internal radiation, cancer induction - to illustrate the margins of uncertainty in the predictions. According to the author safety aspects should not just be seen as a purely technical problem, starting with the fact that nuclear energy is desirable and then ensuring that all required safety regulations are met. Safety aspects are a social problem and should be considered by first discussing whether nuclear energy is acceptable, taking into consideration such consequences as the effects of possible accidents and the long term effects of reactor operation. (C.F.)

  18. Perceptual load in different regions of the visual scene and its relevance for driving.

    Science.gov (United States)

    Marciano, Hadas; Yeshurun, Yaffa

    2015-06-01

    The aim of this study was to better understand the role played by perceptual load, at both central and peripheral regions of the visual scene, in driving safety. Attention is a crucial factor in driving safety, and previous laboratory studies suggest that perceptual load is an important factor determining the efficiency of attentional selectivity. Yet, the effects of perceptual load on driving were never studied systematically. Using a driving simulator, we orthogonally manipulated the load levels at the road (central load) and its sides (peripheral load), while occasionally introducing critical events at one of these regions. Perceptual load affected driving performance at both regions of the visual scene. Critically, the effect was different for central versus peripheral load: Whereas load levels on the road mainly affected driving speed, load levels on its sides mainly affected the ability to detect critical events initiating from the roadsides. Moreover, higher levels of peripheral load impaired performance but mainly with low levels of central load, replicating findings with simple letter stimuli. Perceptual load has a considerable effect on driving, but the nature of this effect depends on the region of the visual scene at which the load is introduced. Given the observed importance of perceptual load, authors of future studies of driving safety should take it into account. Specifically, these findings suggest that our understanding of factors that may be relevant for driving safety would benefit from studying these factors under different levels of load at different regions of the visual scene. © 2014, Human Factors and Ergonomics Society.

  19. A qualified presumption of safety approach for the safety assessment of Grana Padano whey starters.

    Science.gov (United States)

    Rossetti, Lia; Carminati, Domenico; Zago, Miriam; Giraffa, Giorgio

    2009-03-15

    A Qualified Presumption of Safety (QPS) approach was applied to dominant lactic acid bacteria (LAB) associated with Grana Padano cheese whey starters. Thirty-two strains belonging to Lactobacillus helveticus, Lactobacillus delbrueckii subsp. lactis, Streptococcus thermophilus, and Lactobacillus fermentum, and representing the overall genotypic LAB diversity associated with 24 previously collected whey starters [Rossetti, L., Fornasari, M.E., Gatti, M., Lazzi, C., Neviani, E., Giraffa, G., 2008. Grana Padano cheese whey starters: microbial composition and strain distribution. International Journal of Food Microbiology 127, 168-171], were analyzed. All L. helveticus, L. delbrueckii subsp. lactis, and S. thermophilus isolates were susceptible to four (i.e. vancomycin, gentamicin, tetracycline, and erythromycin) of the clinically most relevant antibiotics. One L. fermentum strain displayed phenotypic resistance to tetracycline (Tet(R)), with MIC of 32 microg/ml, and gentamycin (Gm(R)), with MIC of 32 microg/ml. PCR was applied to this strain to test the presence of genes tet(L), tet(M), tet(S), and aac(6')-aph(2')-Ia, which are involved in horizontal transfer of Tet(R) and Gm(R), respectively but no detectable amplification products were observed. According to QPS criteria, we conclude that Grana cheese whey starters do not present particular safety concerns.

  20. Defining safety culture and the nexus between safety goals and safety culture. 1. An Investigation Study on Practical Points of Safety Management

    International Nuclear Information System (INIS)

    Hasegawa, Naoko; Takano, Kenichi; Hirose, Ayako

    2001-01-01

    among those of existing questionnaires about safety culture, organizational climate, and individual safety consciousness. From the results of investigations, it was supposed that the establishment of a safety management system to which the whole organization is committed and that has top-down and bottom-up cycles is necessary to enhance organization safety. For example, it was clarified that employee safety consciousness is relevant to 'the action of safety management section' and to two kinds of organization climate, i.e., 'good human relationship' and 'frequent discussion on safety'. As for worker motivation for safety, it was clarified that commitment to safety activities was directly influenced by 'safety activities adhering to actual work sites', 'advance check', and 'frequent discussion on safety' as a result of correlation analysis among traits of safety activity, attitude during daily work, and organizational climate (Fig. 1). In addition, it was also supposed that the commitment was influenced by 'good human relationship', 'pride in work', and 'communication between head office and work sites' indirectly according to the result of the same analysis. Thus, it is supposed that ideas to make safety activities adhere to actual work sites and good human relationships are necessary for organization safety as well as for the establishment of the safety management system. The state of the organization and work sites before the safety system and activities are enforced must also be assessed. According to the results, the construction, chemical, and manufacturing industries differed in types of safety systems and activities conducted because the system types and activities to be conducted depended on the type of work or work site. Hence, to diagnose an organization and to provide an appropriate safety system and activities that reflect the diagnosis are important to enforce safety culture from the viewpoint of usability and interface of the safety management system

  1. Ensuring ecology safety, furthering the development of nuclear energy

    International Nuclear Information System (INIS)

    Shang Zhaorong; Chen Xiaoqiu; Tang Senming

    2008-01-01

    Ecology safety is as important as political safety, national defense safety, economy safety, food safety, etc. The nuclear power development is an important step for the national energy structure optimization, ecology caring, and implementing sustainable development. The aquatic ecology is important on disposal of low-level liquid waste and cooling water from NPPs and nuclear fuel cycle facilities, and people pay more attention to ecology impact and human threat from the nuclear energy. The author describes relevant ecology problems correlated with nuclear energy such as impact of thermal discharge, ecology sensitive zone, ecology restoration, etc. in order to emphasis that development of nuclear energy should guarantee ecology safety for the sustainable development of nuclear energy. (authors)

  2. Oligonucleotide-based pharmaceuticals: Non-clinical and clinical safety signals and non-clinical testing strategies.

    Science.gov (United States)

    Mustonen, Enni-Kaisa; Palomäki, Tiina; Pasanen, Markku

    2017-11-01

    Antisense oligonucleotides, short interfering RNAs (siRNAs) and aptamers are oligonucleotide-based pharmaceuticals with a promising role in targeted therapies. Currently, five oligonucleotide-based pharmaceuticals have achieved marketing authorization in Europe or USA and many more are undergoing clinical testing. However, several safety concerns have been raised in non-clinical and clinical studies. Oligonucleotides share properties with both chemical and biological pharmaceuticals and therefore they pose challenges also from the regulatory point of view. We have analyzed the safety data of oligonucleotides and evaluated the applicability of current non-clinical toxicological guidelines for assessing the safety of oligonucleotide-based pharmaceuticals. Oligonucleotide-based pharmaceuticals display a similar toxicological profile, exerting adverse effects on liver and kidney, evoking hematological alterations, as well as causing immunostimulation and prolonging the coagulation time. It is possible to extrapolate some of these effects from non-clinical studies to humans. However, evaluation strategies for genotoxicity testing of "non-natural" oligonucleotides should be revised. Additionally, the selective use of surrogates and prediction of clinical endpoints for non-clinically observed immunostimulation is complicated by its multiple potential manifestations, demanding improvements in the testing strategies. Utilizing more relevant and mechanistic-based approaches and taking better account of species differences, could possibly improve the prediction of relevant immunological/proinflammatory effects in humans. Copyright © 2017 Elsevier Inc. All rights reserved.

  3. Divergent effects of transformational and passive leadership on employee safety.

    Science.gov (United States)

    Kelloway, E Kevin; Mullen, Jane; Francis, Lori

    2006-01-01

    The authors concurrently examined the impact of safety-specific transformational leadership and safety-specific passive leadership on safety outcomes. First, the authors demonstrated via confirmatory factor analysis that safety-specific transformational leadership and safety-specific passive leadership are empirically distinct constructs. Second, using hierarchical regression, the authors illustrated, contrary to a stated corollary of transformational leadership theory (B. M. Bass, 1997), that passive leadership contributes incrementally to the prediction of organizationally relevant outcomes, in this case safety-related variables, beyond transformational leadership alone. Third, further analyses via structural equation modeling showed that both transformational and passive leadership have opposite effects on safety climate and safety consciousness, and these variables, in turn, predict safety events and injuries. Implications for research and application are discussed. Copyright 2006 APA.

  4. Healthcare professionals? views on feedback of a patient safety culture assessment

    OpenAIRE

    Zwijnenberg, Nicolien C.; Hendriks, Michelle; Hoogervorst-Schilp, Janneke; Wagner, Cordula

    2016-01-01

    Background By assessing patient safety culture, healthcare providers can identify areas for improvement in patient safety culture. To achieve this, these assessment outcomes have to be relevant and presented clearly. The aim of our study was to explore healthcare professionals? views on the feedback of a patient safety culture assessment. Methods Twenty four hospitals participated in a patient safety culture assessment in 2012. Hospital departments received feedback in a report and on a websi...

  5. Safety Criteria and Standards for Bearing Capacity of Foundation

    Directory of Open Access Journals (Sweden)

    Yanlong Li

    2017-01-01

    Full Text Available This paper focuses on the evaluation standards of factor of safety for foundation stability analysis. The problem of foundation stability is analyzed via the methods of risk analysis of engineering structures and reliability-based design, and the factor of safety for foundation stability is determined by using bearing capacity safety-factor method (BSFM and strength safety-factor method (SSFM. Based on a typical example, the admissible factors of safety were calibrated with a target reliability index specified in relevant standards. Two safety criteria and their standards of bearing capacity of foundation for these two methods (BSFM and SSFM were established. The universality of the safety criteria and their standards for foundation reliability was verified based on the concept of the ratio of safety margin (RSM.

  6. KIT safety management. Annual report 2013; KIT-Sicherheitsmanagement. Jahresbericht 2013

    Energy Technology Data Exchange (ETDEWEB)

    Frank, Gerhard (ed.)

    2014-07-01

    The KIT Safety Management Service Unit (KSM) guarantees radiological and conventional technical safety and security of Karlsruhe Institute of Technology and controls the implementation and observation of legal environmental protection requirements. KSM is responsible for licensing procedures, industrial safety organization, control of environmental protection measures, planning and implementation of emergency preparedness and response, operation of radiological laboratories and measurement stations, extensive radiation protection support and the execution of security tasks in and for all organizational units of KIT. Moreover, KSM is in charge of wastewater and environmental monitoring for all facilities and nuclear installations all over the KIT campus. KSM is headed by the Safety Commissioner of KIT, who is appointed by the Presidential Committee. Within his scope of procedure for KIT, the Safety Commissioner controls the implementation of and compliance with safety-relevant requirements. The KIT Safety Management is certified according to DIN EN ISO 9001, its laboratories are accredited according to DIN EN ISO/IEC 17025. To the extent possible, KSM is committed to maintaining competence in radiation protection and to supporting research and teaching activities. The present reports lists the individual tasks of the KIT Safety Management and informs about the results achieved in 2013. Status figures in principle reflect the status at the end of the year 2013. The processes described cover the areas of competence of KSM. Due to changes in the organization of the infrastructural service units in KIT, KSM has been cancelled at the end of 2013. Its tasks will mainly be covered in 2014 by the new founded service unit Safety and Environmental (Sicherheit und Umwelt, SUM). The departments Campus Security, Fire Brigade and Information Technology have been transferred to the Service Unit General Services (Allgemeine Services, ASERV).

  7. A methodological study to compare survey-based and observation-based evaluations of organisational and safety cultures and then compare both approaches with markers of the quality of care.

    Science.gov (United States)

    Freeth, D; Sandall, J; Allan, T; Warburton, F; Berridge, E J; Mackintosh, N; Rogers, M; Abbott, S

    2012-05-01

    Patient safety concerns have focused attention on organisational and safety cultures, in turn directing attention to the measurement of organisational and safety climates. First, to compare levels of agreement between survey- and observation-based measures of organisational and safety climates/cultures and to compare both measures with criterion-based audits of the quality of care, using evidence-based markers drawn from national care standards relating to six common clinical conditions. (This required development of an observation-based instrument.) Second, to examine whether observation-based evaluations could replace or augment survey measurements to mitigate concerns about declining response rates and increasing social desirability bias. Third, to examine mediating factors in safety and organisational climate scores. The study had three strands: (A) a postal questionnaire survey to elicit staff perceptions of organisational and safety climates, using six prevalidated scales; (B) semistructured non-participant observation of clinical teams; and (C) a retrospective criterion-based audit carried out by non-clinical auditors to minimise hindsight bias. Standardised summary scores were created for each strand, and pairs of measurements were compared (strand A with strand B, strand A with strand C, and strand B with strand C) using Bland-Altman plots to evaluate agreement. Correlations were also examined. Multilevel modelling of Strand A scores explored mediating factors. Eight emergency departments and eight maternity units in England, UK. None. Examination of feasibility, correlation and agreement. Strand A: the overall response rate was 27.6%, whereas site-specific rates ranged from 9% to 47%. We identified more mediating factors than previous studies; variable response rates had little effect on the results. Organisational and safety climate scores were strongly correlated (r = 0.845) and exhibited good agreement [standard deviation (SD) differences 0.449; 14 (88

  8. Mobility Network and Safety

    Directory of Open Access Journals (Sweden)

    Adriana Galderisi

    2010-04-01

    Full Text Available Mobility network is crucial for ensuring territorial safety with respect to natural and technological hazards. They represent a basic support to community’s everyday life although being exposed elements often characterized by high vulnerability to different hazards and, in the meanwhile, strategic equipments for emergency management. Physical damages or the lack in functioning of those networks may greatly increase the loss of human lives caused by hazardous events as well as produce relevant economic damages at medium and long term. Although the relevance of the mobility networks in assuring territorial safety is at present largely recognized, risk analyses have been long focused on buildings’ vulnerability or, even where they have paid attention to mobility network, they have been mainly focused on the physical damages that a given hazard could may induce on individual elements of such network. It is recent the awareness that mobility network represents a system, characterized by relevant interdependences both among its elements and among network infrastructures and urban systems. Based on these assumptions, this paper points out the heterogeneous aspects of the mobility network vulnerability and their relevance in increasing the overall territorial or urban vulnerability to hazardous events. Therefore, an in-depth investigation of the concept of mobility network vulnerability is provided, in order to highlight the aspects mostly investigated and more recent research perspectives. Finally, a case study in the Campania Region is presented in order to point out how traditional risk analyses, generally referred to individual hazards, can sometimes led to invest in the mobility network improvement or development which, targeted to increase the security of a territory result, on the opposite, in an increase of the territorial vulnerability.

  9. Preparation of NPP Dukovany periodic safety review

    International Nuclear Information System (INIS)

    Dubsky, L.; Vymazal, P.

    2004-01-01

    Dukovany NPP in Czech Republic performs a periodic safety review for the second time after approximately 20 years of operation. The history of the Safety Report and its transformation into an internationally accepted form complying with IAEA standards is described. The deterministic and probabilistic assessment of the plant's safety-related design and state is applied to determine whether and to what extend the relevant protective goals are fulfilled by the existing plant design. A description of the step-by-step process is presented together with the creation of methods and criteria for PSR evaluation prepared by Nuclear Research Institute Rez

  10. Study of fundamental safety-related aspects in connection with the decommissioning of nuclear installations. Pt. 2. Safety considerations and emissions

    International Nuclear Information System (INIS)

    John, T.; Thierfeldt, S.

    1993-01-01

    The procedures used so far for the examination of selected decommissioning projects in expert opinions on safety, in particular of nuclear power plants, were screened, with special emphasis on the examination of safety considerations, i.e. analysis of possible accidents. Generic examinations on safety in connection with the decommissioning of nuclear installations were used to assess safety considerations. Different approaches were taken with regard to the selection of analysed accidents and determination of parameters defining activity release and assumptions in safety opinions. Therefore it seems to be appropriate to establish a scenario to be used for nuclear power plant accident analyses, which covers the range of radiologically relevant accidents during decommissioning activities. Although it might be controversially discussed, because of specific plant designs (test and prototype reactors as well as first power reactors), to establish such a radiologically covering accident scenario for older nuclear power plants, it seems to be no problem for modern light water reactors. The radiologically most relevant possible accident in a decommissioned nuclear power plant is fire in the plant. Parameter values and assumptions are suggested which determine the source term in the event of a fire in the plant. Inspite of a conservative determination of parameter values and assumptions, an environmental dose commitment of less than 50 mSv is to be expected for the resulting source term. (orig.) [de

  11. Anticipation and the adaptive control of safety margins in driving

    NARCIS (Netherlands)

    van der Hulst, M.; Meijman, T.F.; Rothengatter, J.A.

    Driving is a task that requires the timely detection of critical events and relevant changes in traffic circumstances. Adaptation of speed and safety margins allows drivers to control the time available to react to potential hazards. One of the basic safety margins in driving is the time headway

  12. For beginners in anaesthesia, self-training with an audiovisual checklist improves safety during anaesthesia induction: A prospective, randomised, controlled two-centre study.

    Science.gov (United States)

    Beck, Stefanie; Reich, Christian; Krause, Dorothea; Ruhnke, Bjarne; Daubmann, Anne; Weimann, Jörg; Zöllner, Christian; Kubitz, Jens

    2018-01-31

    Beginners in residency programmes in anaesthesia are challenged because working environment is complex, and they cannot rely on experience to meet challenges. During this early stage, residents need rules and structures to guide their actions and ensure patient safety. We investigated whether self-training with an electronic audiovisual checklist app on a mobile phone would produce a long-term improvement in the safety-relevant actions during induction of general anaesthesia. During the first month of their anaesthesia residency, we randomised 26 residents to the intervention and control groups. The study was performed between August 2013 and December 2014 in two university hospitals in Germany. In addition to normal training, the residents of the intervention group trained themselves on well tolerated induction using the electronic checklist for at least 60 consecutive general anaesthesia inductions. After an initial learning phase, all residents were observed during one induction of general anaesthesia. The primary outcome was the number of safety items completed during this anaesthesia induction. Secondary outcomes were similar observations 4 and 8 weeks later. Immediately, and 4 weeks after the first learning phase, residents in the intervention group completed a significantly greater number of safety checks than residents in the control group 2.8 [95% confidence interval (CI) 0.4 to 5.1, P = 0.021, Cohen's d = 0.47] and 3.7 (95% CI 1.3 to 6.1, P = 0.003, Cohen's d = 0.61), respectively. The difference between the groups had disappeared by 8 weeks: mean difference in the number of safety checks at 8 weeks was 0.4, 95% CI -2.0 to 2.8, P = 0.736, Cohen's d = 0.07). The use of an audiovisual self-training checklists improves safety-relevant behaviour in the early stages of a residency training programme in anaesthesia.

  13. Climate and climate-related issues for the safety assessment SR-Site

    International Nuclear Information System (INIS)

    2010-12-01

    The purpose of this report is to document current scientific knowledge on climate and climate-related conditions, relevant to the long-term safety of a KBS-3 repository, to a level required for an adequate treatment in the safety assessment SR-Site. The report also presents a number of dedicated studies on climate and selected climate-related processes of relevance for the assessment of long term repository safety. Based on this information, the report presents a number of possible future climate developments for Forsmark, the site selected for building a repository for spent nuclear fuel in Sweden (Figure 1-1). The presented climate developments are used as basis for the selection and analysis of SR-Site safety assessment scenarios in the SR-Site main report /SKB 2011/. The present report is based on research conducted and published by SKB as well as on research reported in the general scientific literature

  14. Climate and climate-related issues for the safety assessment SR-Site

    Energy Technology Data Exchange (ETDEWEB)

    2010-12-15

    The purpose of this report is to document current scientific knowledge on climate and climate-related conditions, relevant to the long-term safety of a KBS-3 repository, to a level required for an adequate treatment in the safety assessment SR-Site. The report also presents a number of dedicated studies on climate and selected climate-related processes of relevance for the assessment of long term repository safety. Based on this information, the report presents a number of possible future climate developments for Forsmark, the site selected for building a repository for spent nuclear fuel in Sweden (Figure 1-1). The presented climate developments are used as basis for the selection and analysis of SR-Site safety assessment scenarios in the SR-Site main report /SKB 2011/. The present report is based on research conducted and published by SKB as well as on research reported in the general scientific literature

  15. Geosphere process report for the safety assessment SR-Site

    International Nuclear Information System (INIS)

    Skagius, Kristina

    2010-11-01

    This report documents geosphere processes identified as relevant to the long-term safety of a KBS-3 repository, and forms an important part of the reporting of the safety assessment SR-Site. The detailed assessment methodology, including the role of the process reports in the assessment, is described in the SR-Site Main report /SKB 2011/

  16. Geosphere process report for the safety assessment SR-Site

    Energy Technology Data Exchange (ETDEWEB)

    Skagius, Kristina (ed.) (Kemakta Konsult AB, Stockholm (Sweden))

    2010-11-15

    This report documents geosphere processes identified as relevant to the long-term safety of a KBS-3 repository, and forms an important part of the reporting of the safety assessment SR-Site. The detailed assessment methodology, including the role of the process reports in the assessment, is described in the SR-Site Main report /SKB 2011/

  17. New IAEA guidance on safety culture

    International Nuclear Information System (INIS)

    Haage, Monica; )

    2012-01-01

    Monica Haage described a project for Kozloduy Nuclear Power Plant in Bulgaria which was also funded by the Norwegian government. This project included the development of guidance documents and training on self-assessment and continuous improvement of safety culture. A draft IAEA safety culture survey was also developed as part of this project in collaboration with St Mary's University, Canada. This project was conducted in parallel with an IAEA project to develop new safety reports on safety culture self-assessment and continuous improvement. A safety report on safety culture during the pre-operational phases of NPPs has also been drafted. The IAEA approach to safety culture assessment was outlined and core principles of the approach were discussed. These include the use of several assessment methods (survey, interview, observation, focus groups, document review), and two distinct levels of analysis. The first is a descriptive analysis of the observed cultural characteristics from each assessment method and overarching themes. This is followed by a 'normative' analysis comparing what has been observed with the desirable characteristics of a strong, positive, safety culture, as defined by the IAEA safety culture framework. The application of this approach during recent Operational Safety Assessment Review Team (OSART) missions was described along with key learning points

  18. Human reliability in probabilistic safety assessments

    International Nuclear Information System (INIS)

    Nunez Mendez, J.

    1989-01-01

    Nowadays a growing interest in medioambiental aspects is detected in our country. It implies an assessment of the risk involved in the industrial processess and installations in order to determine if those are into the acceptable limits. In these safety assessments, among which PSA (Probabilistic Safety Assessments), can be pointed out the role played by the human being in the system is one of the more relevant subjects. (This relevance has been demostrated in the accidents happenned). However in Spain there aren't manuals specifically dedicated to asses the human contribution to risk in the frame of PSAs. This report aims to improve this situation providing: a) a theoretical background to help the reader in the understanding of the nature of the human error, b) a guide to carry out a Human Reliability Analysis and c) a selected overwiev of the techniques and methodologies currently applied in this area. (Author)

  19. The safety culture of the nuclear plants of Sydkraft. Appendices 5-7

    International Nuclear Information System (INIS)

    Edmondson, B.; Firing, J.A.; Nordland, O.S.; Ottne, E.

    1994-01-01

    This separate volume of appendices contains three contributions: ''Safety in Nuclear Electric'' by Bryan Edmondson, which reviews the legislation for nuclear safety in Britain, reproduces the Health and Policy Statement by Nuclear Electric, and describes the management of health and safety in the company. ''Safety in Norwegian off-shore industry'' by Joergen A. Firing, describing the safety practices of the Statoil Group and reproducing the relevant Norwegian law. ''The safety management in SAS Airline. The safety and quality in airline industries'' by O.S. Nordland and E. Ottne describing safety organization, internal control systems, and education and training in SAS

  20. Evaluating a Website to Teach Children Safety with Dogs: A Randomized Controlled Trial

    Directory of Open Access Journals (Sweden)

    David C. Schwebel

    2016-12-01

    Full Text Available Dog bites represent a significant threat to child health. Theory-driven interventions scalable for broad dissemination are sparse. A website was developed to teach children dog safety via increased knowledge, improved cognitive skills in relevant domains, and increased perception of vulnerability to bites. A randomized controlled trial was conducted with 69 children aged 4–5 randomly assigned to use the dog safety website or a control transportation safety website for ~3 weeks. Assessment of dog safety knowledge and behavior plus skill in three relevant cognitive constructs (impulse control, noticing details, and perspective-taking was conducted both at baseline and following website use. The dog safety website incorporated interactive games, instructional videos including testimonials, a motivational rewards system, and messaging to parents concerning child lessons. Our results showed that about two-thirds of the intervention sample was not adherent to website use at home, so both intent-to-treat and per-protocol analyses were conducted. Intent-to-treat analyses yielded mostly null results. Per-protocol analyses suggested children compliant to the intervention protocol scored higher on knowledge and recognition of safe behavior with dogs following the intervention compared to the control group. Adherent children also had improved scores post-intervention on the cognitive skill of noticing details compared to the control group. We concluded that young children’s immature cognition can lead to dog bites. Interactive eHealth training on websites shows potential to teach children relevant cognitive and safety skills to reduce risk. Compliance to website use is a challenge, and some relevant cognitive skills (e.g., noticing details may be more amenable to computer-based training than others (e.g., impulse control.

  1. Organizational factors in nuclear safety

    International Nuclear Information System (INIS)

    Wilpert, Bernhard

    2000-01-01

    The overall picture of factors which contributed to the event presents a panorama of a NPP where organizational and managerial characteristics were intricately intertwined and emerged as crucial for a general deterioration of the plant's capabilities to continually correct its deficiencies and optimize its operations. In the following author shall attempt to first cover various important efforts to modeling organizational factors relevant to safety. The second part of my presentation will offer an attempt towards an integrative model. The third part concludes with an agenda for research and practice. Most of the twelve different approaches above attempt to consider safety relevant organizational factors by way of pragmatic classifications. Together with their sub-categories we can count close to 160 different factors on various levels of abstraction. This is tantamount to say that most approaches lack systematic theoretical underpinnings. Thus then arises the question whether we need to develop a generic model, which promises to encompass these three major approaches altogether. Practical issues emerge particularly in the domain of organizational development, i.e. the goal oriented efforts to change the structures and the functioning of nuclear operations in such a way that the desired outputs in terms safety and reliability result in a sustained fashion. Again, these practical concerns are intimately related to developments and advances in theory and methodology. Only a close cooperation among scientists from various disciplines and of practitioners holds the promise of adequately understanding and use of organizational factors in future improving the safety record of nuclear industry worldwide. (S.Y.)

  2. Design aspects of radiological safety in nuclear facilities

    International Nuclear Information System (INIS)

    Patkulkar, D.S.; Purohit, R.G.; Tripathi, R.M.

    2014-01-01

    In order to keep operational performance of a nuclear facility high and to keep occupational and public exposure ALARA, radiological safety provisions must be reviewed at the time of facility design. Deficiency in design culminates in deteriorated system performance and non adherence to safety standards and could sometimes result in radiological incident. Important radiological aspects relevant to safety were compiled based on operating experiences, design deficiencies brought out from past nuclear incidents, experience gained during maintenance, participation in design review of upcoming nuclear facilities and radiological emergency preparedness

  3. The Nordic programme for nuclear safety 1990-1993

    International Nuclear Information System (INIS)

    Soerensen, H.C.

    1993-04-01

    The supplement contains a name-and-address list relevant to the Nordic Nuclear Safety Programme 1990-1993 and covering consortiums, reference groups, programme coordinators, project leaders and project participants. (AB)

  4. The Nordic programme for nuclear safety 1990-1993

    International Nuclear Information System (INIS)

    Soerensen, H.C.

    1992-03-01

    The supplement contains a name-and-address list relevant to the Nordic Nuclear Safety Programme 1990-1993 and covering consortiums, reference groups, programme coordinators, project leaders and project participants. (AB)

  5. A novel safety assessment strategy applied to non-selective extracts.

    Science.gov (United States)

    Koster, Sander; Leeman, Winfried; Verheij, Elwin; Dutman, Ellen; van Stee, Leo; Nielsen, Lene Munch; Ronsmans, Stefan; Noteborn, Hub; Krul, Lisette

    2015-06-01

    A main challenge in food safety research is to demonstrate that processing of foodstuffs does not lead to the formation of substances for which the safety upon consumption might be questioned. This is especially so since food is a complex matrix in which the analytical detection of substances, and consequent risk assessment thereof, is difficult to determine. Here, a pragmatic novel safety assessment strategy is applied to the production of non-selective extracts (NSEs), used for different purposes in food such as for colouring purposes, which are complex food mixtures prepared from reference juices. The Complex Mixture Safety Assessment Strategy (CoMSAS) is an exposure driven approach enabling to efficiently assess the safety of the NSE by focussing on newly formed substances or substances that may increase in exposure during the processing of the NSE. CoMSAS enables to distinguish toxicologically relevant from toxicologically less relevant substances, when related to their respective levels of exposure. This will reduce the amount of work needed for identification, characterisation and safety assessment of unknown substances detected at low concentration, without the need for toxicity testing using animal studies. In this paper, the CoMSAS approach has been applied for elderberry and pumpkin NSEs used for food colouring purposes. Copyright © 2015 Elsevier Ltd. All rights reserved.

  6. Regulatory assessment of safety culture in nuclear organisations - current trends and challenges

    International Nuclear Information System (INIS)

    Tronea, M.

    2010-01-01

    The paper gives an overview of the current practices in the area of regulatory assessment of safety culture in nuclear organisations and of the associated challenges. While the assessment and inspection procedures currently in use by regulatory authorities worldwide are directed primarily at verifying compliance with the licensing basis, there is a recognised need for a more systematic approach to the identification, collection and review of data relevant to the safety culture in licensees' organisations. The paper presents a proposal for using the existing regulatory inspection practices for gathering information relevant to safety culture and for assessing it in an integrated manner. The proposal is based on the latest requirements and guidance issued by the International Atomic Energy Agency (IAEA) on management systems for nuclear facilities and activities, particularly as regards the attributes needed for a strong nuclear safety culture. (author)

  7. ENSI Approach to Oversight of Safety Culture

    International Nuclear Information System (INIS)

    Humbel Haag, Claudia

    2012-01-01

    Claudia Humbel Haag presented developments in ENSI approach to safety culture oversight. ENSI has developed a definition/understanding of Safety Culture and a concept of how to perform oversight of Safety Culture. ENSI defines safety culture in the following way: Safety Culture comprises the behaviour, world views (in the sense of conceptualisations of reality and explanation models), values (in the sense of aims and evaluation scales), and features of the physical environment (specifically, the nuclear power plant and the documents used) which are shared by many members of an organization, in as much as these are of significance to nuclear safety. A model of the accessibility of safety culture was presented ranging from the observable (external aspects of safety culture), to aspects that are accessible by asking questions, through to aspects that are not accessible (internal part of safety culture). ENSI considers observable aspects through the existing systematic safety assessment compliance program. Aspects that are observable by asking questions will be addressed by additional oversight activities outside the systematic assessment program. Aspects that are not accessible are addressed by helping the licensee to re-think its safety culture through proactive discussions on safety culture. Reports are issued to the licensee on assumptions and observations identified through the discussions. The conclusions of the presentation emphasised the importance of basing any interventions in this area on a solid understanding of the concept of safety culture. ENSI safety culture oversight principles were also described. These include licensee responsibility for safety, and the need for the regulator to critically review their own activities to ensure a positive influence on the licensee

  8. The safety of a novel early mobilization protocol conducted by ICU physicians: a prospective observational study

    Directory of Open Access Journals (Sweden)

    Keibun Liu

    2018-02-01

    Full Text Available Abstract Background There are numerous barriers to early mobilization (EM in a resource-limited intensive care unit (ICU without a specialized team or an EM culture, regarding patient stability while critically ill or in the presence of medical devices. We hypothesized that ICU physicians can overcome these barriers. The aim of this study was to investigate the safety of EM according to the Maebashi EM protocol conducted by ICU physicians. Methods This was a single-center prospective observational study. All consecutive patients with an unplanned emergency admission were included in this study, according to the exclusion criteria. The observation period was from June 2015 to June 2016. Data regarding adverse events, medical devices in place during rehabilitation, protocol adherence, and rehabilitation outcomes were collected. The primary outcome was safety. Results A total of 232 consecutively enrolled patients underwent 587 rehabilitation sessions. Thirteen adverse events occurred (2.2%; 95% confidence interval, 1.2–3.8% and no specific treatment was needed. There were no instances of dislodgement or obstruction of medical devices, tubes, or lines. The incidence of adverse events associated with mechanical ventilation or extracorporeal membrane oxygenation (ECMO was 2.4 and 3.6%, respectively. Of 587 sessions, 387 (66% sessions were performed at the active rehabilitation level, including sitting out of the bed, active transfer to a chair, standing, marching, and ambulating. ICU physicians attended over 95% of these active rehabilitation sessions. Of all patients, 143 (62% got out of bed within 2 days (median 1.2 days; interquartile range 0.1–2.0. Conclusions EM according to the Maebashi EM protocol conducted by ICU physicians, without a specialized team or EM culture, was performed at a level of safety similar to previous studies performed by specialized teams, even with medical devices in place, including mechanical ventilation or ECMO

  9. Regulatory Regime and its influence in the nuclear safety

    International Nuclear Information System (INIS)

    Laaksonen, J.

    1999-01-01

    A leading internationally agreed principle is that the prime responsibility for nuclear safety rests with each user of nuclear energy. A proper regulatory regime is needed to ensure that this responsibility is met. In the first place it provides a verification that all relevant safety issues are understood and taken into account in the practical measures by the users but it is equally important that the regulatory regime supports the users in their strive to achieve an adequate level of safety (author)

  10. NKS/SOS-1 seminar on safety analysis

    Energy Technology Data Exchange (ETDEWEB)

    Lauridsen, K. [Risoe National Lab., Roskilde (Denmark); Anderson, K. [Karinta-Konsult (Sweden); Pulkkinen, U. [VTT Automation (Finland)

    2001-05-01

    The report describes presentations and discussions at a seminar held at Risoe on March 22-23, 2000. The title of the seminar was NKS/SOS-1 - Safety Analysis. It dealt with issues of relevance for the safety analysis for the entire nuclear safety field (notably reactors and nuclear waste repositories). Such issues were: objectives of safety analysis, risk criteria, decision analysis, expert judgement and risk communication. In addition, one talk dealt with criteria for chemical industries in Europe. The seminar clearly showed that the concept of risk is multidimensional, which makes clarity and transparency essential elements in risk communication, and that there are issues of common concern between different applications, such as how to deal with different kinds of uncertainty and expert judgement. (au)

  11. Enhancement of safety for reprocessing facilities

    International Nuclear Information System (INIS)

    2012-06-01

    The adequacy of the safety measures for utility loss accidents in nuclear fuel reprocessing facilities which have been formulated by the nuclear enterprises is investigated in JNES which organizes an advanced committee to specifically study this problem. The results are reviewed in the present report including the case of such severe accidents as in Fukushima Daiichi Nuclear Power Plant. The report also represents a tentative proposal for examination standards of such unimaginable severe accidents as 'station blackout,' urgent safety measures necessary for reoperation of nuclear power plants and requested by nuclear and industrial safety agency, and pointing out and clarification of the potential weakness from the safety point of view, and collective and composite evaluation of safety of the relevant facilities. Furthermore, the definition of accident management is given as of controlled condition and the authorized way of thinking for the cases of plural events happening at the same time and the cases when risks exist radioactivity emits with explosion. (S. Ohno)

  12. Safety and toxicological evaluation of a novel, water-soluble undenatured type II collagen.

    Science.gov (United States)

    Yoshinari, Orie; Marone, Palma Ann; Moriyama, Hiroyoshi; Bagchi, Manashi; Shiojima, Yoshiaki

    2013-09-01

    This study was conducted to determine the broad-spectrum safety of a novel, water-soluble undenatured type II collagen (NEXT-II) derived from chicken sternum cartilage. The presence of epitope in NEXT-II was confirmed by using a commercial kit. The acute oral LD₅₀ of NEXT-II was found to be greater than 5000 mg/kg bw in rats, while the single-dose acute dermal LD₅₀ was greater than 2000 mg/kg bw. The primary dermal irritation index (PDII) of NEXT-II was found to be 1.8 and classified as slightly irritating to the skin. In primary eye irritation studies, the maximum mean total score (MMTS) of NEXT-II was observed to be 7.3 and classified as minimally irritating to the eye. Long-term safety studies were conducted in dogs over a period of 150 d, and no significant changes were observed in body weight, heart rate, respiration rate and blood chemistry. NEXT-II does not induce mutagenicity in the bacterial reverse mutation test in five Salmonella typhimurium strains either with or without metabolic activation. Furthermore, two experiments were conducted to assess the potential of NEXT-II to induce mutations with and without metabolic activation at the mouse lymphoma thymidine kinase locus using the cell line L5178Y. No biologically relevant increase of mutants was observed. Also, no dose-dependent toxicity was observed. Furthermore, colony sizing showed no clastogenic effects induced by NEXT-II under the experimental conditions. These studies demonstrated the broad spectrum of safety of NEXT-II.

  13. Experience of safety monitoring in the context of a prospective observational study of artemether-lumefantrine in rural Tanzania: lessons learned for pharmacovigilance reporting

    Directory of Open Access Journals (Sweden)

    Kabanywanyi Abdunoor M

    2010-07-01

    Full Text Available Abstract Objectives To identify and implement strategies that help meet safety monitoring requirements in the context of an observational study for artemether-lumefantrine (AL administered as first-line treatment for uncomplicated malaria in rural Tanzania. Methods Pharmacovigilance procedures were developed through collaboration between the investigating bodies, the relevant regulatory authority and the manufacturer of AL. Training and refresher sessions on the pharmacovigilance system were provided for healthcare workers from local health facilities and field recorders of the Ifakara Health Demographic Surveillance System (IHDSS. Three distinct channels for identification of adverse events (AEs and serious adverse events (SAEs were identified and implemented. Passive reporting took place through IHDSS and health care facilities, starting in October 2007. The third channel was through solicited reporting that was included in the context of a survey on AL as part of the ALIVE (Artemether-Lumefantrine In Vulnerable patients: Exploring health impact study (conducted only in March-April 2008. Results Training was provided for 40 healthcare providers (with refresher training 18 months later and for six field recorders. During the period 1st September 2007 to 31st March 2010, 67 AEs were reported including 52 under AL, five under sulphadoxine-pyrimethamine, one under metakelfin, two after antibiotics; the remaining seven were due to anti-pyretic or anti-parasite medications. Twenty patients experienced SAEs; in 16 cases, a relation to AL was suspected. Six of the 20 cases were reported within 24 hours of occurrence. Discussion Safety monitoring and reporting is possible even in settings with weak health infrastructure. Reporting can be enhanced by regular and appropriate training of healthcare providers. SMS text alerts provide a practical solution to communication challenges. Conclusion Experience gained in this setting could help to improve

  14. How Productive Is Workplace Health and Safety?

    DEFF Research Database (Denmark)

    Buhai, I. Sebastian; Cottini, Elena; Westergaard-Nielsen, Niels

    2017-01-01

    In this paper, we investigate the causal impact of workplace health and safety practices on firm performance, using Danish longitudinal matched employer–employee data merged with unique cross-sectional representative firm survey data on work environment conditions. We estimate standard production...... functions, augmented with workplace environment indicators, addressing both time-invariant and time-varying potentially relevant unobservables in the production process. We find positive and large productivity effects of improved physical dimensions of the health and safety environment, specifically...

  15. Relevance of passive safety testing at the fast flux test facility to advanced liquid metal reactors - 5127

    International Nuclear Information System (INIS)

    Wootan, D.W.; Omberg, R.P.

    2015-01-01

    Significant cost and safety improvements can be realized in advanced liquid metal reactor (LMR) designs by emphasizing inherent or passive safety through crediting the beneficial reactivity feedbacks associated with core and structural movement. This passive safety approach was adopted for the Fast Flux Test Facility (FFTF), and an experimental program was conducted to characterize the structural reactivity feedback. Testing at the Rapsodie and EBR-II reactors had demonstrated the beneficial effect of reactivity feedback caused by changes in fuel temperature and core geometry mechanisms in a liquid metal fast reactor in a holistic sense. The FFTF passive safety testing program was developed to examine how specific design elements influenced dynamic reactivity feedback in response to a reactivity input and to demonstrate the scalability of reactivity feedback results from smaller cores like Rapsodie and EBR-II to reactor cores that were more prototypic in scale to reactors of current interest. The U.S. Department of Energy, Office of Nuclear Energy Advanced Reactor Technology program is in the process of preserving, protecting, securing, and placing in electronic format information and data from the FFTF, including the core configurations and data collected during the passive safety tests. Evaluation of these actual test data could provide insight to improve analytical methods which may be used to support future licensing applications for LMRs. (authors)

  16. Patient safety risk factors in minimally invasive surgery : A validation study

    NARCIS (Netherlands)

    Rodrigues, S.P.; Ter Kuile, M.; Dankelman, J.; Jansen, F.W.

    2012-01-01

    This study was conducted to adapt and validate a patient safety (PS) framework for minimally invasive surgery (MIS) as a first step in understanding the clinical relevance of various PS risk factors in MIS. Eight patient safety risk factor domains were identified using frameworks from a systems

  17. The safety and effectiveness profile of eldecalcitol in a prospective, post-marketing observational study in Japanese male patients with osteoporosis.

    Science.gov (United States)

    Kondo, Satoshi; Kakihata, Hiroyuki; Nishida, Yosuke; Furuno, Yuko; Kobayashi, Yumiko; Tabata, Hidehiro; Nomura, Makoto

    2018-03-12

    We conducted a post-marketing observational study to investigate the safety and effectiveness of eldecalcitol for the treatment of osteoporosis in a Japanese clinical setting. The observation period was 12 months for women and 36 months for men. The final results for the female patients have already been published. In this article, the final results for the male patients are reported. A total of 470 male osteoporosis patients were enrolled. The safety analysis set included 431 patients (mean age, 76.8 years; mean ± SD follow-up period, 631.0 ± 450.3 days), and 175 patients continued treatment throughout the 3-year observational period. Adverse drug reactions (ADRs) were reported in 28 patients (6.49%); the most common ADRs were hypercalcemia (1.16%) and renal impairment (1.16%). Serious ADRs were reported in 5 patients (1.16%). Mean serum calcium was within the normal range throughout the observation period. The cumulative incidence of new vertebral and nonvertebral fractures at 36 months, estimated by Kaplan-Meier analysis, was 10.23 and 4.06%, respectively. At the last observation, mean lumbar spine bone mineral density was 3.49% higher (P effectiveness of eldecalcitol for the treatment of Japanese male osteoporosis patients was confirmed in clinical practice. Careful monitoring of serum calcium and estimated glomerular filtration rate, both before and during treatment, is necessary to minimize the risk of hypercalcemia and renal impairment while maximizing the effectiveness of eldecalcitol.

  18. Safety Culture Monitoring: How to Assess Safety Culture in Real Time?

    International Nuclear Information System (INIS)

    Zronek, B.; Maryska, J.; Treslova, L.

    2016-01-01

    Do you know what is current level of safety culture in your company? Are you able to follow trend changes? Do you know what your recent issues are? Since safety culture is understood as vital part of nuclear industry daily life, it is crucial to know what the current level is. It is common to perform safety culture survey or ad hoc assessment. This contribution shares Temelin NPP, CEZ approach how to assess safety culture level permanently. Using behavioral related outputs of gap solving system, observation program, dedicated surveys, regulatory assessment, etc., allows creating real time safety culture monitoring without the need to perform any other activities. (author)

  19. Improving construction site safety through leader-based verbal safety communication.

    Science.gov (United States)

    Kines, Pete; Andersen, Lars P S; Spangenberg, Soren; Mikkelsen, Kim L; Dyreborg, Johnny; Zohar, Dov

    2010-10-01

    The construction industry is one of the most injury-prone industries, in which production is usually prioritized over safety in daily on-site communication. Workers have an informal and oral culture of risk, in which safety is rarely openly expressed. This paper tests the effect of increasing leader-based on-site verbal safety communication on the level of safety and safety climate at construction sites. A pre-post intervention-control design with five construction work gangs is carried out. Foremen in two intervention groups are coached and given bi-weekly feedback about their daily verbal safety communications with their workers. Foremen-worker verbal safety exchanges (experience sampling method, n=1,693 interviews), construction site safety level (correct vs. incorrect, n=22,077 single observations), and safety climate (seven dimensions, n=105 questionnaires) are measured over a period of up to 42 weeks. Baseline measurements in the two intervention and three control groups reveal that foremen speak with their workers several times a day. Workers perceive safety as part of their verbal communication with their foremen in only 6-16% of exchanges, and the levels of safety at the sites range from 70-87% (correct observations). Measurements from baseline to follow-up in the two intervention groups reveal that safety communication between foremen and workers increases significantly in one of the groups (factor 7.1 increase), and a significant yet smaller increase is found when the two intervention groups are combined (factor 4.6). Significant increases in the level of safety are seen in both intervention groups (7% and 12% increases, respectively), particularly in regards to 'access ways' and 'railings and coverings' (39% and 84% increases, respectively). Increases in safety climate are seen in only one of the intervention groups with respect to their 'attention to safety.' No significant trend changes are seen in the three control groups on any of the three measures

  20. Modelling of particular phenomena observed in PANDA with Gothic

    International Nuclear Information System (INIS)

    Bandurski, Th.; Putz, F.; Andreani, M.; Analytis, M.

    2000-01-01

    PANDA is a large scale facility for investigating the long-term decay heat removal from the containment of a next generation 'passive' Advanced Light Water Reactor (ALWR). The first test series was aimed at the investigation of the long-term LOCA response of the Passive Containment Cooling System (PCCS) for the General Electric (GE) Simplified Boiling Water Reactor (SBWR). Recently, the facility is used in the framework of two European projects for investigating the performance of four passive cooling systems, i.e. the Building Condenser (BC) designed by Siemens for the SWR-1000 long-term containment cooling, the Passive Containment Cooling System for the European Simplified Boiling Water Reactor (ESBWR), the Containment Plate Condenser (CPC) and the Isolation Condenser (IC) for cooling of a BWR core. The PANDA tests have the dual objectives of improving confidence in the performance of the passive heat removal mechanisms underlying the design of the tested safety systems and extending the data base available for containment analysis code qualification. Among others, the containment analysis code Gothic was chosen for the analysis of particular phenomena observed during the PANDA tests. Ibis paper presents selected safety relevant phenomena observed in the PANDA tests and identified for the analyses and possible approaches for their modeling with Gothic. (author)

  1. An Investigation of Health and Safety Measures in a Hydroelectric Power Plant.

    Science.gov (United States)

    Acakpovi, Amevi; Dzamikumah, Lucky

    2016-12-01

    Occupational risk management is known as a catalyst in generating superior returns for all stakeholders on a sustainable basis. A number of companies in Ghana implemented health and safety measures adopted from international companies to ensure the safety of their employees. However, there exist great threats to employees' safety in these companies. The purpose of this paper is to investigate the level of compliance of Occupational Health and Safety management systems and standards set by international and local legislation in power producing companies in Ghana. The methodology is conducted by administering questionnaires and in-depth interviews as measuring instruments. A random sampling technique was applied to 60 respondents; only 50 respondents returned their responses. The questionnaire was developed from a literature review and contained questions and items relevant to the initial research problem. A factor analysis was also carried out to investigate the influence of some variables on safety in general. Results showed that the significant factors that influence the safety of employees at the hydroelectric power plant stations are: lack of training and supervision, non-observance of safe work procedures, lack of management commitment, and lack of periodical check on machine operations. The study pointed out the safety loopholes and therefore helped improve the health and safety measures of employees in the selected company by providing effective recommendations. The implementation of the proposed recommendations in this paper, would lead to the prevention of work-related injuries and illnesses of employees as well as property damage and incidents in hydroelectric power plants. The recommendations may equally be considered as benchmark for the Safety and Health Management System with international standards.

  2. Safety aspects of the modernization of I and C and process information in nuclear power plants with special regard to alarm annunciation

    Energy Technology Data Exchange (ETDEWEB)

    Seidel, F [Bundesamt fuer Strahlenschutz, Salzgitter (Germany)

    1997-09-01

    In particular for older German nuclear power plants there are projects to modernize I and C and process information systems. This modernization mainly aims at improvements in plant operation. For instance, using modern computing technology, the plant operation can be optimized, according to further details. Furthermore, the problem of spare-part keeping for out-dated components can be solved. For modernizing the I and C or the process computer system, safety-relevant aspects have to be taken into account. For instance, the compatibility of the system modification with the existing alarm annunciation concept shall be considered, and for each modernization step, the interfaces between the equipment of different safety significance shall be assessed and observed. The functions and the associated equipment have to be qualified in accordance to their safety significance. At present, the regulatory framework for computer-based instrumentation and control as well as for information systems is being elaborated in Germany and worldwide. Recently, the guidelines of the German Reactor Safety Commission have been extended with regard to the introduction and safety application of modern computer-based I and C in nuclear power plants. Furthermore, some of the essential requirements for design and qualification of modern I and C can be derived from the existing rules and standards. Particularly, concerning the alarm annunciation system, this report summarizes safety-relevant aspects of the modernization of the instrumentation and control system as well as the process information system in nuclear power plants. (author). 4 refs.

  3. Safety aspects of the modernization of I and C and process information in nuclear power plants with special regard to alarm annunciation

    International Nuclear Information System (INIS)

    Seidel, F.

    1997-01-01

    In particular for older German nuclear power plants there are projects to modernize I and C and process information systems. This modernization mainly aims at improvements in plant operation. For instance, using modern computing technology, the plant operation can be optimized, according to further details. Furthermore, the problem of spare-part keeping for out-dated components can be solved. For modernizing the I and C or the process computer system, safety-relevant aspects have to be taken into account. For instance, the compatibility of the system modification with the existing alarm annunciation concept shall be considered, and for each modernization step, the interfaces between the equipment of different safety significance shall be assessed and observed. The functions and the associated equipment have to be qualified in accordance to their safety significance. At present, the regulatory framework for computer-based instrumentation and control as well as for information systems is being elaborated in Germany and worldwide. Recently, the guidelines of the German Reactor Safety Commission have been extended with regard to the introduction and safety application of modern computer-based I and C in nuclear power plants. Furthermore, some of the essential requirements for design and qualification of modern I and C can be derived from the existing rules and standards. Particularly, concerning the alarm annunciation system, this report summarizes safety-relevant aspects of the modernization of the instrumentation and control system as well as the process information system in nuclear power plants. (author). 4 refs

  4. Relevant Organizational Factors for Social Efficiency in the Road Transport Sector; Procesos Organizativos Clave para la Eficiencia Social en el Transporte por Carretera

    Energy Technology Data Exchange (ETDEWEB)

    Silla, I; Gamero, N

    2011-12-27

    Previous research has emphasized the need to consider the social dimension featuring organizations in order to maximize organizational efficiency (Rasmussen, 1997). In the road transport sector, previous research has focused on the relationship between human factor, stress, fatigue, and other relevant issues, and professional drivers health and safety (p.e., De Croon et al, 2004). However, research on relevant organizational factors is scarce. This study aims to examine the association between leadership and supportive climate, and employees health and safety. Moreover, the impact of stress (time pressure) was also examined because previous research has stressed its importance. This study used a sample of 486 employees from 35 different Spanish companies pertaining to the road transport sector. Findings showed time pressure to be negatively associated to employees health, job satisfaction and satisfaction with safety. Additionally, leadership was positively associated employees health, job satisfaction and satisfaction with safety. Finally, co-workers and supervisors supportive climate was positively associated with job satisfaction and negatively associated to illness. These findings have relevant practical implications for the competitiveness of road transport companies. (Author) 21 refs.

  5. Safety evaluation of synthetic β-carotene

    NARCIS (Netherlands)

    Woutersen, R.A.; Wolterbeek, A.P.M.; Appel, M.J.; Berg, H. van den; Goldbohm, R.A.; Feron, V.J.

    1999-01-01

    The safety of β-carotene was reassessed by evaluating the relevant literature on the beneficial and adverse effects of β-carotene on cancer and, in particular, by evaluating the results of toxicity studies. β- Carotene appeared neither genotoxic nor reprotoxic or teratogenic, and no signs of organ

  6. Evaluating an Entertainment–Education Telenovela to Promote Workplace Safety

    Directory of Open Access Journals (Sweden)

    Diego E. Castaneda

    2013-08-01

    Full Text Available Occupational safety and health professionals worked with health communication experts to collaborate with a major Spanish language television network to develop and implement a construction workplace safety media intervention targeting Latino/Hispanic audiences. An Entertainment–Education (EE health communication strategy was used to create a worksite safety storyline weaved into the main plot of a nationally televised Telenovela (Spanish language soap opera. A secondary analysis of audience survey data in a pre/posttest cross-sectional equivalent group design was performed to evaluate the effectiveness of this EE media intervention to change knowledge, attitudes, and intention outcomes related to the prevention of fatal falls at construction worksites. Results indicate that using culturally relevant mediums can be an effective way of reaching and educating audiences about specific fall prevention information. This is aligned with recommendations by the Institute of Medicine (IOM to increase interventions and evaluations of culturally relevant and competent health communication.

  7. Safety climate and firefighting: Focus group results.

    Science.gov (United States)

    DeJoy, David M; Smith, Todd D; Dyal, Mari-Amanda

    2017-09-01

    Firefighting is a hazardous occupation and there have been numerous calls for fundamental changes in how fire service organizations approach safety and balance safety with other operational priorities. These calls, however, have yielded little systematic research. As part of a larger project to develop and test a model of safety climate for the fire service, focus groups were used to identify potentially important dimensions of safety climate pertinent to firefighting. Analyses revealed nine overarching themes. Competency/professionalism, physical/psychological readiness, and that positive traits sometimes produce negative consequences were themes at the individual level; cohesion and supervisor leadership/support at the workgroup level; and politics/bureaucracy, resources, leadership, and hiring/promotion at the organizational level. A multi-level perspective seems appropriate for examining safety climate in firefighting. Safety climate in firefighting appears to be multi-dimensional and some dimensions prominent in the general safety climate literature also seem relevant to firefighting. These results also suggest that the fire service may be undergoing transitions encompassing mission, personnel, and its fundamental approach to safety and risk. These results help point the way to the development of safety climate measures specific to firefighting and to interventions for improving safety performance. Copyright © 2017 National Safety Council and Elsevier Ltd. All rights reserved.

  8. Human Reliability in Probabilistic Safety Assessments

    International Nuclear Information System (INIS)

    Nunez Mendez, J.

    1989-01-01

    Nowadays a growing interest in environmental aspects is detected in our country. It implies an assessment of the risk involved in the industrial processes and installations in order to determine if those are into the acceptable limits. In these safety assessments, among which PSA (Probabilistic Safety Assessments), can be pointed out the role played by the human being in the system is one of the more relevant subjects (This relevance has been demonstrated in the accidents happened) . However, in Spain there aren't manuals specifically dedicated to asses the human contribution to risk in the frame of PSAs. This report aims to improve this situation providing: a) a theoretical background to help the reader in the understanding of the nature of the human error, b) a quid to carry out a Human Reliability Analysis and c) a selected overview of the techniques and methodologies currently applied in this area. (Author) 20 refs

  9. Which aspects of safety culture predict incident reporting behavior in neonatal intensive care units? A multilevel analysis

    NARCIS (Netherlands)

    Snijders, Cathelijne; Kollen, Boudewijn J.; van Lingen, Richard A.; Fetter, Willem P. F.; Molendijk, Harry; Kok, J. H.; te Pas, E.; Pas, H.; van der Starre, C.; Bloemendaal, E.; Lopes Cardozo, R. H.; Molenaar, A. M.; Giezen, A.; van Lingen, R. A.; Maat, H. E.; Molendijk, A.; Snijders, C.; Lavrijssen, S.; Mulder, A. L. M.; de Kleine, M. J. K.; Koolen, A. M. P.; Schellekens, M.; Verlaan, W.; Vrancken, S.; Fetter, W. P. F.; Schotman, L.; van der Zwaan, A.; van der Tuijn, Y.; Tibboel, D.; van der Schaaf, T. W.; Klip, H.; Kollen, B. J.

    2009-01-01

    OBJECTIVES: Safety culture assessments are increasingly used to evaluate patient-safety programs. However, it is not clear which aspects of safety culture are most relevant in understanding incident reporting behavior, and ultimately improving patient safety. The objective of this study was to

  10. Safety assessment and verification for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2001-01-01

    This publication supports the Safety Requirements on the Safety of Nuclear Power Plants: Design. This Safety Guide was prepared on the basis of a systematic review of all the relevant publications including the Safety Fundamentals, Safety of Nuclear Power Plants: Design, current and ongoing revisions of other Safety Guides, INSAG reports and other publications that have addressed the safety of nuclear power plants. This Safety Guide also provides guidance for Contracting Parties to the Convention on Nuclear Safety in meeting their obligations under Article 14 on Assessment and Verification of Safety. The Safety Requirements publication entitled Safety of Nuclear Power Plants: Design states that a comprehensive safety assessment and an independent verification of the safety assessment shall be carried out before the design is submitted to the regulatory body. This publication provides guidance on how this requirement should be met. This Safety Guide provides recommendations to designers for carrying out a safety assessment during the initial design process and design modifications, as well as to the operating organization in carrying out independent verification of the safety assessment of new nuclear power plants with a new or already existing design. The recommendations for performing a safety assessment are suitable also as guidance for the safety review of an existing plant. The objective of reviewing existing plants against current standards and practices is to determine whether there are any deviations which would have an impact on plant safety. The methods and the recommendations of this Safety Guide can also be used by regulatory bodies for the conduct of the regulatory review and assessment. Although most recommendations of this Safety Guide are general and applicable to all types of nuclear reactors, some specific recommendations and examples apply mostly to water cooled reactors. Terms such as 'safety assessment', 'safety analysis' and 'independent

  11. Effectiveness and safety of different duration of thromboprophylaxis in 16,865 hip replacement patients - A real-word, prospective observational study

    DEFF Research Database (Denmark)

    Pedersen, Alma B; Sorensen, Henrik Toft; Mehnert, Frank

    2015-01-01

    the effectiveness and safety of short (1-6 days) and standard (7-27 days) compared with extended (>/=28 days) thromboprophylaxis using population-based design. MATERIAL AND METHODS: Among all primary THR procedures performed in Denmark from 2010 through 2012 (n=16,865), we calculated adjusted hazard ratios (a...... or death. CONCLUSIONS: In a real-word observational cohort of unselected THR patients, we observed no difference in the risks of symptomatic VTE, VTE/ death or bleeding with respect to thromboprophylaxis duration....

  12. Experience relevant to safety obtained from reactor decommissioning operations in the French Atomic Energy Commission

    International Nuclear Information System (INIS)

    Giraudel, B.; Langlois, G.

    1979-01-01

    From among the nuclear facilities constructed in France the authors cite eight large reactors, ranging from critical assemblies to power reactors, that have been finally shut-down since 1965. A brief account is given of the way in which the various operations were carried out after the final control rod drop, a distinction being drawn between the shut-down proper and the containment and dismantling work. A description is also given, from the technical and regulatory standpoint, of the final stage attained, and mention is made of French safety arrangements and of the part played by the safety services during decommissioning operations. Among the lessons derived from French experience, the authors mention the completion of operations without any serious safety problems, and with guarantees for the protection of personnel and the population as a whole, by conventional techniques; the advantage of planning decommissioning operations from the very beginning of construction of the facilities; and the importance of filing descriptive documents. In view of the experience gained, the French Atomic Energy Commission has devised internal procedures for facilitating the application of regulations governing the shut-down and decommissioning phases, which are aimed at preserving surveillance procedures similar to those in force during normal operation. (author)

  13. Exposure of nickel and the relevance of nickel sensitivity among hospital cleaners

    Energy Technology Data Exchange (ETDEWEB)

    Clemmensen, O J; Menne, T; Kaaber, K; Solgaard, P

    1981-01-01

    The nickel content of water specimens from consecutive stages during the cleaning process in a Danish hospital was analyzed. Statistically significant increases of the nickel concentrations were found from step to step of the cleaning, eventually exceeding the theoretical sensitizing safety limit. The relevance of the findings in relation to hand eczema is discussed.

  14. Stress Tests Worldwide - IAEA Nuclear Safety Action Plan

    International Nuclear Information System (INIS)

    Lyons, J.E.

    2012-01-01

    The IAEA nuclear safety action plan relies on 11 important issues. 1) Safety assessments in light of the Fukushima accident: the IAEA secretariat will develop a methodology for stress tests against specific extreme natural hazards and will provide assistance for their implementation; 2) Strengthen existing IAEA peer reviews; 3) Emergency preparedness and response; 4) National Regulatory bodies in terms of independence and adequacy of human and financial resources; 5) The development of safety culture and scientific and technical capacity in Operating Organizations; 6) The upgrading of IAEA safety standards in a more efficient way; 7) A better implementation of relevant conventions concerning nuclear safety and nuclear accidents; 8) To provide a broad assistance on safety standard for countries embarking on a nuclear power program; 9) To facilitate the use of available information, expertise and techniques concerning radiation protection; 10) To enhance the transparency of nuclear industry; and 11) To promote the cooperation between member states in nuclear safety. (A.C.)

  15. Safety standards for wind turbines; Sicherheitsnormen fuer Windenergieanlagen

    Energy Technology Data Exchange (ETDEWEB)

    Boyce, K. [Underwriters Laboratories Inc., Northbrook, IL (United States)

    2012-08-15

    As the global wind infrastructure sustains rapid growth, compliance with relevant standards provide validation of design principles and establish due diligence in addressing critical attributes such as safety. The IEC 61400 series of standards provides important information for addressing safety and performance of wind turbine systems. Efforts to address unique issues within the United States market has led to development of two safety standards, UL 6141 for large wind turbines and UL 6142 for small wind turbines. These standards, which are being published as American National Standards, contain key safety requirements for the electrical system, electrical safety and controls system, grid connection, and related safety issues. In the future, collaborative efforts will lead to continued exchange of best practices and opportunities for broader harmonization. Development of these standards, and their use by the manufacturing community in design and development of wind turbine products, supports maximal safety and performance of the burgeoning wind infrastructure. (orig.)

  16. Application range affected by software failures in safety relevant instrumentation and control systems of nuclear power plants

    International Nuclear Information System (INIS)

    Jopen, Manuela; Mbonjo, Herve; Sommer, Dagmar; Ulrich, Birte

    2017-03-01

    This report presents results that have been developed within a BMUB-funded research project (Promotion Code 3614R01304). The overall objective of this project was to broaden the knowledge base of GRS regarding software failures and their impact in software-based instrumentation and control (I and C) systems. To this end, relevant definitions and terms in standards and publications (DIN, IEEE standards, IAEA standards, NUREG publications) as well as in the German safety requirements for nuclear power plants were analyzed first. In particular, it was found that the term ''software fault'' is defined differently and partly contradictory in the considered literature sources. For this reason, a definition of software fault was developed on the basis of the software life cycle of software-based I and C systems within the framework of this project, which takes into account the various aspects relevant to software faults and their related effects. It turns out that software failures result from latent faults in a software-based control system, which can lead to a non-compliant behavior of a software-based I and C system. Hereby a distinction should be made between programming faults and specification faults. In a further step, operational experience with software failures in software-based I and C systems in nuclear facilities and in nonnuclear sector was investigated. The identified events were analyzed with regard to their cause and impacts and the analysis results were summarized. Based on the developed definition of software failure and on the COMPSIS-classification scheme for events related to software based I and C systems, the COCS-classification scheme was developed to classify events from operating experience with software failures, in which the events are classified according to the criteria ''cause'', ''affected system'', ''impact'' and ''CCF potential''. This classification scheme was applied to evaluate the events identified in the framework of this project

  17. Radiological Safety Officer (RSO): role and responsibilities

    International Nuclear Information System (INIS)

    Joshi, M.L.; Yadav, J.S.; Gopalakrishnan, R.K.; Ansari, I.A.

    2017-01-01

    The fundamental safety objective in a radiological facility (RF) is to protect people and the environment from harmful effects of ionising radiation. The radiation risks to people and the environment that may arise from the use of radiation and radioactive material must be assessed and must be controlled by means of the application of the relevant standards of safety. Thus, all facilities handling radioactive material must have experts, who are responsible for assisting the plant management in radiation protection programme

  18. Psychological aspects of food safety risk perception

    DEFF Research Database (Denmark)

    Scholderer, Joachim

    signals, motivating approach. Novelty, and the detection of certain olfactory and visual cues associated with spoilage or contamination, act as orientation or threat signals and motivate closer inspection or avoidance. Anticipatory affects are an inherent part of these behaviour regulation systems...... problematic food safety behaviours are likely to occur. The presentation will begin with an overview of the relevant psychological mechanisms that regulate approach and avoidance behaviour with respect to potentially hazardous foods. Learned representations of familiarity and reward value act as safety...

  19. The ConCom Safety Management Scale: developing and testing a measurement instrument for control-based and commitment-based safety management approaches in hospitals.

    Science.gov (United States)

    Alingh, Carien W; Strating, Mathilde M H; van Wijngaarden, Jeroen D H; Paauwe, Jaap; Huijsman, Robbert

    2018-03-06

    Nursing management is considered important for patient safety. Prior research has predominantly focused on charismatic leadership styles, although it is questionable whether these best characterise the role of nurse managers. Managerial control is also relevant. Therefore, we aimed to develop and test a measurement instrument for control-based and commitment-based safety management of nurse managers in clinical hospital departments. A cross-sectional survey design was used to test the newly developed questionnaire in a sample of 2378 nurses working in clinical departments. The nurses were asked about their perceptions of the leadership behaviour and management practices of their direct supervisors. Psychometric properties were evaluated using confirmatory factor analysis and reliability estimates. The final 33-item questionnaire showed acceptable goodness-of-fit indices and internal consistency (Cronbach's α of the subscales range: 0.59-0.90). The factor structure revealed three subdimensions for control-based safety management: (1) stressing the importance of safety rules and regulations; (2) monitoring compliance; and (3) providing employees with feedback. Commitment-based management consisted of four subdimensions: (1) showing role modelling behaviour; (2) creating safety awareness; (3) showing safety commitment; and (4) encouraging participation. Construct validity of the scale was supported by high factor loadings and provided preliminary evidence that control-based and commitment-based safety management are two distinct yet related constructs. The findings were reconfirmed in a cross-validation procedure. The results provide initial support for the construct validity and reliability of our ConCom Safety Management Scale. Both management approaches were found to be relevant for managing patient safety in clinical hospital departments. The scale can be used to deepen our understanding of the influence of patient safety management on healthcare professionals

  20. Probability and uncertainty in nuclear safety decisions

    International Nuclear Information System (INIS)

    Pate-Cornell, M.E.

    1986-01-01

    In this paper, we examine some problems posed by the use of probabilities in Nuclear Safety decisions. We discuss some of the theoretical difficulties due to the collective nature of regulatory decisions, and, in particular, the calibration and the aggregation of risk information (e.g., experts opinions). We argue that, if one chooses numerical safety goals as a regulatory basis, one can reduce the constraints to an individual safety goal and a cost-benefit criterion. We show the relevance of risk uncertainties in this kind of regulatory framework. We conclude that, whereas expected values of future failure frequencies are adequate to show compliance with economic constraints, the use of a fractile (e.g., 95%) to be specified by the regulatory agency is justified to treat hazard uncertainties for the individual safety goal. (orig.)

  1. Radiation and waste safety: Strengthening national capabilities

    International Nuclear Information System (INIS)

    Barretto, P.; Webb, G.; Mrabit, K.

    1997-01-01

    For many years, the IAEA has been collecting information on national infrastructures for assuring safety in applications of nuclear and radiation technologies. For more than a decade, from 1984-95, information relevant to radiation safety particularly was obtained through more than 60 expert missions undertaken by Radiation Protection Advisory Teams (RAPATs) and follow-up technical visits and expert missions. The RAPAT programme documented major weaknesses and the reports provided useful background for preparation of national requests for IAEA technical assistance. Building on this experience and subsequent policy reviews, the IAEA took steps to more systematically evaluate the needs for technical assistance in areas of nuclear and radiation safety. The outcome was the development of an integrated system designed to more closely assess national priorities and needs for upgrading their infrastructures for radiation and waste safety

  2. Other relevant numerical modelling papers

    International Nuclear Information System (INIS)

    Chartier, M.

    1989-01-01

    The ocean modelling is a rapidly evolving science and a large number of results have been published. Several categories of papers are of particular interest for this review: the papers published by the international atomic institutions, such as the NEA (for the CRESP or Subseabed Programs), the IAEA (for example the Safety Series, the Technical Report Series or the TECDOC), and the ICRP, and the papers concerned by more fundamental research, which are published in specific scientific literature. This paper aims to list some of the most relevant publications for the CRESP purposes. It means by no way to be exhaustive, but informative on the incontestable progress recently achieved in that field. One should note that some of these papers are so recent that their final version has not yet been published

  3. Model-Driven Development of Safety Architectures

    Science.gov (United States)

    Denney, Ewen; Pai, Ganesh; Whiteside, Iain

    2017-01-01

    We describe the use of model-driven development for safety assurance of a pioneering NASA flight operation involving a fleet of small unmanned aircraft systems (sUAS) flying beyond visual line of sight. The central idea is to develop a safety architecture that provides the basis for risk assessment and visualization within a safety case, the formal justification of acceptable safety required by the aviation regulatory authority. A safety architecture is composed from a collection of bow tie diagrams (BTDs), a practical approach to manage safety risk by linking the identified hazards to the appropriate mitigation measures. The safety justification for a given unmanned aircraft system (UAS) operation can have many related BTDs. In practice, however, each BTD is independently developed, which poses challenges with respect to incremental development, maintaining consistency across different safety artifacts when changes occur, and in extracting and presenting stakeholder specific information relevant for decision making. We show how a safety architecture reconciles the various BTDs of a system, and, collectively, provide an overarching picture of system safety, by considering them as views of a unified model. We also show how it enables model-driven development of BTDs, replete with validations, transformations, and a range of views. Our approach, which we have implemented in our toolset, AdvoCATE, is illustrated with a running example drawn from a real UAS safety case. The models and some of the innovations described here were instrumental in successfully obtaining regulatory flight approval.

  4. Supplement to safety analysis report. 306-W building operations safety requirement

    International Nuclear Information System (INIS)

    Richey, C.R.

    1979-08-01

    The operations safety requirements (OSRs) presented in this report define the conditions, safe boundaries, and management control needed for safely conducting operations with radioactive materials in the Pacific Northwest Laboratory (PNL) 306-W building. The safety requirements are organized in five sections. Safety limits are safety-related process variables that are observable and measurable. Limiting conditions cover: equipment and technical conditions and characteristics of the facility and operations necessary for continued safe operation. Surveillance requirements prescribe the requirements for checking systems and components that are essential to safety. Equipment design controls require that changes to process equipment and systems be independently checked and approved to assure that the changes will have no adverse effect on safety. Administrative controls describe and discuss the organization and administrative systems and procedures to be used for safe operation of the facility. Details of the implementation of the operations safety requirements are prescribed by internal PNL documents such as criticality safety specifications and radiation work procedures

  5. Influence of information about specific absorption rate (SAR) upon customers' purchase decisions and safety evaluation of mobile phones.

    Science.gov (United States)

    Wiedemann, Peter M; Schütz, Holger; Clauberg, Martin

    2008-02-01

    This study investigated whether the SAR value is a purchase-relevant characteristic of mobile phones for laypersons and what effect the disclosure of a precautionary SAR value has on laypersons' risk perception. The study consisted of two parts: Study part 1 used a conjoint analysis design to explore the relevance of the SAR value and other features of mobile phones for an intended buying decision. Study part 2 used an experimental, repeated measures design to examine the effect of the magnitude of SAR values and the disclosure of a precautionary SAR value on risk perception. In addition, the study included an analysis of prior concerns of the study participants with regard to mobile phone risks. Part 1 indicates that the SAR value has a high relevance for laypersons' purchase intentions. In the experimental purchase setting it ranks even before price and equipment features. The results of study part 2 show that providing information of a precautionary limit value does not influence risk perception. This result suggests that laypersons' underlying subjective "safety model" for mobile phones resembles more a "margin of safety" concept than a threshold concept. The latter observation holds true no matter how concerned the participants are. (c) 2007 Wiley-Liss, Inc.

  6. Radiation Safety of Electromagnetic Waves

    International Nuclear Information System (INIS)

    Hussein, A.Z.

    2009-01-01

    The wide spread of Electromagnetic Waves (EMW) through the power lines, multimedia, communications, devices, appliances, etc., are well known. The probable health hazards associated with EMW and the radiation safety criteria are to be reviewed. However, the principles of the regulatory safety are based on radiation protection procedure, intervention to combat the relevant risk and to mitigate consequences. The oscillating electric magnetic fields (EMF) of the electromagnetic radiation (EMR) induce electrical hazards. The extremely high power EMR can cause fire hazards and explosions of pyrotechnic (Rad Haz). Biological hazards of EMF result as dielectric heat, severe burn, as well as the hazards of eyes. Shielding is among the technical protective measures against EMR hazards. Others are limitation of time of exposure and separation distance apart of the EMR source. Understanding and safe handling of the EMR sources are required to feel safety.

  7. The International Safety Framework for nuclear power source applications in outer space-Useful and substantial guidance

    Science.gov (United States)

    Summerer, L.; Wilcox, R. E.; Bechtel, R.; Harbison, S.

    2015-06-01

    In 2009, the International Safety Framework for Nuclear Power Source Applications in Outer Space was adopted, following a multi-year process that involved all major space faring nations under the auspices of a partnership between the UN Committee on the Peaceful Uses of Outer Space and the International Atomic Energy Agency. The Safety Framework reflects an international consensus on best practices to achieve safety. Following the 1992 UN Principles Relevant to the Use of Nuclear Power Sources in Outer Space, it is the second attempt by the international community to draft guidance promoting the safety of applications of nuclear power sources in space missions. NPS applications in space have unique safety considerations compared with terrestrial applications. Mission launch and outer space operational requirements impose size, mass and other space environment limitations not present for many terrestrial nuclear facilities. Potential accident conditions could expose nuclear power sources to extreme physical conditions. The Safety Framework is structured to provide guidance for both the programmatic and technical aspects of safety. In addition to sections containing specific guidance for governments and for management, it contains technical guidance pertinent to the design, development and all mission phases of space NPS applications. All sections of the Safety Framework contain elements directly relevant to engineers and space mission designers for missions involving space nuclear power sources. The challenge for organisations and engineers involved in the design and development processes of space nuclear power sources and applications is to implement the guidance provided in the Safety Framework by integrating it into the existing standard space mission infrastructure of design, development and operational requirements, practices and processes. This adds complexity to the standard space mission and launch approval processes. The Safety Framework is deliberately

  8. National critical incident reporting systems relevant to anaesthesia: a European survey.

    Science.gov (United States)

    Reed, S; Arnal, D; Frank, O; Gomez-Arnau, J I; Hansen, J; Lester, O; Mikkelsen, K L; Rhaiem, T; Rosenberg, P H; St Pierre, M; Schleppers, A; Staender, S; Smith, A F

    2014-03-01

    Critical incident reporting is a key tool in the promotion of patient safety in anaesthesia. We surveyed representatives of national incident reporting systems in six European countries, inviting information on scope and organization, and intelligence on factors determining success and failure. Some systems are government-run and nationally conceived; others started out as small, specialty-focused initiatives, which have since acquired a national reach. However, both national co-ordination and specialty enthusiasts seem to be necessary for an optimally functioning system. The role of reporting culture, definitional issues, and dissemination is discussed. We make recommendations for others intending to start new systems and speculate on the prospects for sharing patient safety lessons relevant to anaesthesia at European level.

  9. Latest developments on safety analysis methodologies at the Juzbado plant

    International Nuclear Information System (INIS)

    Zurron-Cifuentes, Oscar; Ortiz-Trujillo, Diego; Blanco-Fernandez, Luis A.

    2010-01-01

    Over the last few years the Juzbado Plant has developed and implemented several analysis methodologies to cope with specific issues regarding safety management. This paper describes the three most outstanding of them, so as to say, the Integrated Safety Analysis (ISA) project, the adaptation of the MARSSIM methodology for characterization surveys of radioactive contamination spots, and the programme for the Systematic Review of the Operational Conditions of the Safety Systems (SROCSS). Several reasons motivated the decision to implement such methodologies, such as Regulator requirements, operational experience and of course, the strong commitment of ENUSA to maintain the highest standards of nuclear industry on all the safety relevant activities. In this context, since 2004 ENUSA is undertaking the ISA project, which consists on a systematic examination of plant's processes, equipment, structures and personnel activities to ensure that all relevant hazards that could result in unacceptable consequences have been adequately evaluated and the appropriate protective measures have been identified. On the other hand and within the framework of a current programme to ensure the absence of radioactive contamination spots on unintended areas, the MARSSIM methodology is being applied as a tool to conduct the radiation surveys and investigation of potentially contaminated areas. Finally, the SROCSS programme was initiated earlier this year 2009 to assess the actual operating conditions of all the systems with safety relevance, aiming to identify either potential non-conformities or areas for improvement in order to ensure their high performance after years of operation. The following paragraphs describe the key points related to these three methodologies as well as an outline of the results obtained so far. (authors)

  10. Drug safety evaluation of defibrotide.

    Science.gov (United States)

    Richardson, Paul G; Corbacioglu, Selim; Ho, Vincent Trien-Vinh; Kernan, Nancy A; Lehmann, Leslie; Maguire, Craig; Maglio, Michelle; Hoyle, Margaret; Sardella, Marco; Giralt, Sergio; Holler, Ernst; Carreras, Enric; Niederwieser, Dietger; Soiffer, Robert

    2013-01-01

    Hepatic veno-occlusive disease (VOD), also known as sinusoidal obstruction syndrome (SOS), is a potentially life-threatening complication of chemotherapeutic conditioning used in preparation for hematopoietic stem-cell transplantation (SCT). Defibrotide (DF) has been shown in Phase II and III trials to improve complete response in patients with severe VOD (sVOD). None of the articles, to date, provide a comprehensive review of the safety of DF in VOD and/or a range of other conditions. This article reviews current clinical findings on DF, primarily in terms of safety for use in treatment and prophylaxis of VOD, and relevant safety data for its use in other diseases. The literature review was conducted using a PubMed search with the fixed term 'defibrotide' in combination with ≥ 1 of 'safety', 'veno-occlusive disease' (with and without 'treatment', 'prevention'), 'oncology', 'myeloma', 'microangiopathy', 'anti-thrombotic' and 'peripheral vascular disorder'. Related articles from the EBMT and ASH conference websites were also included. DF was well tolerated in majority of the studies. The safety profile of DF is largely favourable with toxicities comparable to control populations in the setting of SCT complicated by sVOD.

  11. Safety culture and quality management of Kartini research reactor

    International Nuclear Information System (INIS)

    Syarip; Hauptmanns, Ulrich

    1999-01-01

    The evaluation for assessing the safety culture and quality of safety management of Kartini research reactor is presented. The method is based on the concept of management control of safety (audit) as well as by using the developed method i.e. the questionnaires concerning areas of relevance which have to be answered with value statements. There are seven statements or qualifiers in answering the questions. Since such statements are vague, they are represented by fuzzy numbers. The weaknesses can be identified from the different areas contemplated. The evaluation result show that the quality of safety management of Kartini research reactor is globally rated as 'Average'. The operator behavior in the implementation of 'safety culture' concept is found as a weakness, therefore this area should be improved. (author)

  12. Summary report on safety objectives in nuclear power plants

    International Nuclear Information System (INIS)

    1989-01-01

    The special Task Force on Safety Objectives of the Commission of the European Communities (CEC) Working Group on the Safety of Light Water Reactors reported in May 1983 on its review of existing overall safety objectives in nuclear power plants. Since then much relevant worlwide activity has taken place. This report reviews those activities that have taken place since 1983 in European Community Member States, including more recent Members, as well as in Sweden and Finland. The report confines itself to issues related to probabilistic safety objectives, and concludes that significant progress has been made in many areas. Mutual understanding of safety objectives is leading to a convergence of views and approaches, but it is noted that much work remains to be completed

  13. Regulatory Expectations for Safety Culture

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Su Jin; Oh, Jang Jin; Choi, Young Sung [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2014-05-15

    The oversight of licensee's safety culture becomes an important issue that attracts great public and political concerns recently in Korea. Beginning from the intended violation of rules, a series of corruptions, documents forgery and disclosure of wrong-doings made the public think that the whole mindset of nuclear workers has been inadequate. Thus, they are demanding that safety culture shall be improved and that regulatory body shall play more roles and responsibilities for the improvements and oversight for them. This paper introduces, as an effort of regulatory side, recent changes in the role of regulators in safety culture, regulatory expectations on the desired status of licensee's safety culture, the pilot inspection program for safety culture and research activity for the development of oversight system. After the Fukushima accident in Japan 2011, many critics has searched for cultural factors that caused the unacceptable negligence pervaded in Japan nuclear society and the renewed emphasis has been placed on rebuilding safety culture by operators, regulators, and relevant institutions globally. Significant progress has been made in how to approach safety culture and led to a new perspective different from the existing normative assessment method both in operators and regulatory side. Regulatory expectations and oversight of them are based on such a new holistic concept for human, organizational and cultural elements to maintain and strengthen the integrity of defense in depth and consequently nuclear safety.

  14. Regulatory Expectations for Safety Culture

    International Nuclear Information System (INIS)

    Jung, Su Jin; Oh, Jang Jin; Choi, Young Sung

    2014-01-01

    The oversight of licensee's safety culture becomes an important issue that attracts great public and political concerns recently in Korea. Beginning from the intended violation of rules, a series of corruptions, documents forgery and disclosure of wrong-doings made the public think that the whole mindset of nuclear workers has been inadequate. Thus, they are demanding that safety culture shall be improved and that regulatory body shall play more roles and responsibilities for the improvements and oversight for them. This paper introduces, as an effort of regulatory side, recent changes in the role of regulators in safety culture, regulatory expectations on the desired status of licensee's safety culture, the pilot inspection program for safety culture and research activity for the development of oversight system. After the Fukushima accident in Japan 2011, many critics has searched for cultural factors that caused the unacceptable negligence pervaded in Japan nuclear society and the renewed emphasis has been placed on rebuilding safety culture by operators, regulators, and relevant institutions globally. Significant progress has been made in how to approach safety culture and led to a new perspective different from the existing normative assessment method both in operators and regulatory side. Regulatory expectations and oversight of them are based on such a new holistic concept for human, organizational and cultural elements to maintain and strengthen the integrity of defense in depth and consequently nuclear safety

  15. Safety leadership: application in construction site.

    Science.gov (United States)

    Cooper, Dominic

    2010-01-01

    The extant safety literature suggests that managerial Safety Leadership is vital to the success and maintenance of a behavioral safety process. The current paper explores the role of Managerial Safety Leadership behaviors in the success of a behavioral safety intervention in the Middle-East with 47,000 workers from multiple nationalities employed by fourteen sub-contractors and one main contractor. A quasi-experimental repeating ABABAB, within groups design was used. Measurement focused on managerial Safety Leadership and employee safety behaviors as well as Corrective Actions. Data was collected over 104 weeks. During this time, results show safety behavior improved by 30 percentage points from an average of 65% during baseline to an average of 95%. The site achieved 121 million man-hours free of lost-time injuries on the longest run. Stepwise multiple regression analyses indicated 86% of the variation in employee safety behavior was associated with senior, middle and front-line manager's Safety Leadership behaviors and the Corrective Action Rate. Approximately 38% of the variation in the Total Recordable Incident Rate (TRIR) was associated with the Observation rate, Corrective Action Rate and Observers Records of managerial safety leaders (Visible Ongoing Support). The results strongly suggest manager's Safety Leadership influences the success of Behavioral Safety processes.

  16. Trends in Surface Level Ozone Observations from Human-health Relevant Metrics: Results from the Tropospheric Ozone Assessment Report (TOAR)

    Science.gov (United States)

    Fleming, Z. L.; von Schneidemesser, E.; Doherty, R. M.; Malley, C.; Cooper, O. R.; Pinto, J. P.; Colette, A.; Xu, X.; Simpson, D.; Schultz, M.; Hamad, S.; Moola, R.; Solberg, S.; Feng, Z.

    2017-12-01

    Ozone is an air pollutant formed in the atmosphere from precursor species (NOx, VOCs, CH4, CO) that is detrimental to human health and ecosystems. The global Tropospheric Ozone Assessment Report (TOAR) initiative has assembled a global database of surface ozone observations and generated ozone exposure metrics at thousands of measurement sites around the world. This talk will present results from the assessment focused on those indicators most relevant to human health. Specifically, the trends in ozone, comparing different time periods and patterns across regions and among metrics will be addressed. In addition, the fraction of population exposed to high ozone levels and how this has changed between 2000 and 2014 will also be discussed. The core time period analyzed for trends was 2000-2014, selected to include a greater number of sites in East Asia. Negative trends were most commonly observed at many US and some European sites, whereas many sites in East Asia showed positive trends, while sites in Japan showed more of a mix of positive and negative trends. More than half of the sites showed a common direction and significance in the trends for all five human-health relevant metrics. The peak ozone metrics indicate a reduction in exposure to peak levels of ozone related to photochemical episodes in Europe and the US. A considerable number of European countries and states within the US have shown a decrease in population-weighted ozone over time. The 2000-2014 results will be augmented and compared to the trend analysis for additional time periods that cover a greater number of years, but by necessity are based on fewer sites. Trends are found to be statistically significant at a larger fraction of sites with longer time series, compared to the shorter (2000-2014) time series.

  17. Efficacy and safety of moxifloxacin in acute exacerbations of chronic bronchitis: a prospective, multicenter, observational study (AVANTI

    Directory of Open Access Journals (Sweden)

    Chuchalin Alexander

    2013-01-01

    Full Text Available Abstract Background Acute exacerbations of chronic bronchitis (AECB, including chronic obstructive pulmonary disease (AECOPD, represent a substantial patient burden. Few data exist on outpatient antibiotic management for AECB/AECOPD in Eastern/South Eastern Europe, in particular on the use of moxifloxacin (Avelox®, although moxifloxacin is widely approved in this region based on evidence from international clinical studies. Methods AVANTI (AVelox® in Acute Exacerbations of chroNic bronchiTIs was a prospective, observational study conducted in eight Eastern European countries in patients > 35 years with AECB/AECOPD to whom moxifloxacin was prescribed. In addition to safety and efficacy outcomes, data on risk factors and the impact of exacerbation on daily life were collected. Results In the efficacy population (N = 2536, chronic bronchitis had been prevalent for > 10 years in 31.4% of patients and 66.0% of patients had concomitant COPD. Almost half the patients had never smoked, in contrast to data from Western Europe and the USA, where only one-quarter of COPD patients are non-smokers. The mean number of exacerbations in the last 12 months was 2.7 and 26.3% of patients had been hospitalized at least once for exacerbation. Physician compliance with the recommended moxifloxacin dose (400 mg once daily was 99.6%. The mean duration of moxifloxacin therapy for the current exacerbation (Anthonisen type I or II in 83.1%; predominantly type I was 6.4 ± 1.9 days. Symptom improvement was reported after a mean of 3.4 ± 1.4 days. After 5 days, 93.2% of patients reported improvement and, in total, 93.5% of patients were symptom-free after 10 days. In the safety population (N = 2672, 57 (2.3% patients had treatment-emergent adverse events (TEAEs and 4 (0.15% had serious TEAEs; no deaths occurred. These results are in line with the known safety profile of moxifloxacin. Conclusions A significant number of patients in this

  18. Advanced reactor safety research quarterly report, October-December 1982. Volume 24

    Energy Technology Data Exchange (ETDEWEB)

    None

    1984-04-01

    This report describes progress in a number of activities dealing with current safety issues relevant to both light water reactors (LWRs) and breeder reactors. The work includes a broad range of experiments to simulate accidental conditions to provide the required data base to understand important accident sequences and to serve as a basis for development and verification of the complex computer simulation models and codes used in accident analysis and licensing reviews. Such a program must include the development of analytical models, verified by experiment, which can be used to predict reactor and safety system performance under a broad variety of abnormal conditions. Current major emphasis is focused on providing information to NRC relevant to (1) its deliberations and decisions dealing with severe LWR accidents and (2) its safety evaluation of the proposed Clinch River Breeder Reactor.

  19. Investigational new drug safety reporting requirements for human drug and biological products and safety reporting requirements for bioavailability and bioequivalence studies in humans. Final rule.

    Science.gov (United States)

    2010-09-29

    The Food and Drug Administration (FDA) is amending its regulations governing safety reporting requirements for human drug and biological products subject to an investigational new drug application (IND). The final rule codifies the agency's expectations for timely review, evaluation, and submission of relevant and useful safety information and implements internationally harmonized definitions and reporting standards. The revisions will improve the utility of IND safety reports, reduce the number of reports that do not contribute in a meaningful way to the developing safety profile of the drug, expedite FDA's review of critical safety information, better protect human subjects enrolled in clinical trials, subject bioavailability and bioequivalence studies to safety reporting requirements, promote a consistent approach to safety reporting internationally, and enable the agency to better protect and promote public health.

  20. Methods and processes of developing the Strengthening the Reporting of Observational Studies in Epidemiology - Veterinary (STROBE-Vet) statement

    DEFF Research Database (Denmark)

    Sargeant, J. M.; O'Connor, A. M.; Dohoo, I. R.

    2016-01-01

    and biostatisticians, many of whom hold or have held editorial positionswith relevant journals.Methods: Prior to the meeting, 19 experts completed a survey about whether they felt any of the 22 itemsof the STROBE statement should be modified and if items should be added to address unique issues relatedto observational......Background: The reporting of observational studies in veterinary research presents many challenges thatoften are not adequately addressed in published reporting guidelines.Objective: To develop an extension of the STROBE (Strengthening the Reporting of Observational Studiesin Epidemiology......) statement that addresses unique reporting requirements for observational studies inveterinary medicine related to health, production, welfare, and food safety.Design: A consensus meeting of experts was organized to develop an extension of the STROBE statementto address observational studies in veterinary...

  1. Recommendation for an European wind turbine safety standard

    Energy Technology Data Exchange (ETDEWEB)

    Hjuler Jensen, P.; Hauge Madsen, P.; Winther-Jensen, M.; Machielse, L.; Stam, W.; Einsfeld, V.; Woelfel, E.; Elliot, G.; Wilde, L. de

    1988-09-15

    The objective is to establish an European standard for wind safety which should apply for all member countries of the European Communities. The document contains a list of recommended safety requirements in relation to the system, structure, electrical installations, operation and maintenance of wind turbines. The recommended safety standards cover electricity producing wind turbines connected to electricity grids in both single and cluster applications and with a swept area in excess of 25 square meters and/or a rated power of 10kW. The document should be used in combination with The European Standards for Wind Turbine Loads and other relevant European Standards. Environmental condition, with the emphasis of wind conditions and more extreme climatic conditions, are also considered in relation to safety requirements. (AB).

  2. Teamwork, organizational learning, patient safety and job outcomes.

    Science.gov (United States)

    Goh, Swee C; Chan, Christopher; Kuziemsky, Craig

    2013-01-01

    This article aims to encourage healthcare administrators to consider the learning organization concept and foster collaborative learning among teams in their attempt to improve patient safety. Relevant healthcare, organizational behavior and human resource management literature was reviewed. A patient safety culture, fostered by healthcare leaders, should include an organizational culture that encourages collaborative learning, replaces the blame culture, prioritizes patient safety and rewards individuals who identify serious mistakes. As healthcare institution staffs are being asked to deliver more complex medical services with fewer resources, there is a need to understand how hospital staff can learn from other organizational settings, especially the non-healthcare sectors. The paper provides suggestions for improving patient safety which are drawn from the health and business management literature.

  3. The nuclear safety in France, in 1988

    International Nuclear Information System (INIS)

    1988-08-01

    In the scope of the nuclear safety program, in France, a state of the art of the projects on the 1st August 1988, is given. The different domains related to the nuclear safety are summarized. The purposes, the actions and the available means of the nuclear safety interministerial committee, are examined. The problems concerning the radiation protection of the personnel and reactor components, the application of the regulations and the nuclear materials management, are also examined. In the case of a nuclear accident, the protection operations depend on the responsibilities and on the different fields of action. In the world scale, the international cooperation and the example of the Tchernobyl accident are of relevant importance [fr

  4. Safety assessment and verification for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2004-01-01

    This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. The present publication is a revision of the IAEA Safety Guide on Management of Nuclear Power Plants for Safe Operation issued in 1984. It supplements Section 2 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation. Nuclear power technology is different from the customary technology of power generation from fossil fuel and by hydroelectric means. One major difference between the management of nuclear power plants and that of conventional generating plants is the emphasis that should be placed on nuclear safety, quality assurance, the management of radioactive waste and radiological protection, and the accompanying national regulatory requirements. This Safety Guide highlights the important elements of effective management in relation to these aspects of safety. The attention to be paid to safety requires that the management recognize that personnel involved in the nuclear power programme should understand, respond effectively to, and continuously search for ways to enhance safety in the light of any additional requirements socially and legally demanded of nuclear energy. This will help to ensure that safety policies that result in the safe operation of nuclear power plants are implemented and that margins of safety are always maintained. The structure of the organization, management standards and administrative controls should be such that there is a high degree of assurance that safety policies and decisions are implemented, safety is continuously enhanced and a strong safety culture is promoted and supported. The objective of this publication is to guide Member States in setting up an operating organization which facilitates the safe operation of nuclear power plants to a high level internationally. The second objective is to provide guidance on the most important organizational elements in order to contribute to a strong safety

  5. Safety assessment and verification for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2005-01-01

    This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. The present publication is a revision of the IAEA Safety Guide on Management of Nuclear Power Plants for Safe Operation issued in 1984. It supplements Section 2 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation. Nuclear power technology is different from the customary technology of power generation from fossil fuel and by hydroelectric means. One major difference between the management of nuclear power plants and that of conventional generating plants is the emphasis that should be placed on nuclear safety, quality assurance, the management of radioactive waste and radiological protection, and the accompanying national regulatory requirements. This Safety Guide highlights the important elements of effective management in relation to these aspects of safety. The attention to be paid to safety requires that the management recognize that personnel involved in the nuclear power programme should understand, respond effectively to, and continuously search for ways to enhance safety in the light of any additional requirements socially and legally demanded of nuclear energy. This will help to ensure that safety policies that result in the safe operation of nuclear power plants are implemented and that margins of safety are always maintained. The structure of the organization, management standards and administrative controls should be such that there is a high degree of assurance that safety policies and decisions are implemented, safety is continuously enhanced and a strong safety culture is promoted and supported. The objective of this publication is to guide Member States in setting up an operating organization which facilitates the safe operation of nuclear power plants to a high level internationally. The second objective is to provide guidance on the most important organizational elements in order to contribute to a strong safety

  6. Food safety behaviors observed in celebrity chefs across a variety of programs.

    Science.gov (United States)

    Maughan, Curtis; Chambers, Edgar; Godwin, Sandria

    2017-03-01

    Consumers obtain information about foodborne illness prevention from many sources, including television media. The purpose of this study was to evaluate a variety of cooking shows with celebrity chefs to understand their modeling of food safety behaviors. Cooking shows (100 episodes) were watched from 24 celebrity chefs preparing meat dishes. A tabulation of food safety behaviors was made for each show using a checklist. Proper modeling of food safety behaviors was limited, with many incidences of errors. For example, although all chefs washed their hands at the beginning of cooking at least one dish, 88% did not wash (or were not shown washing) their hands after handling uncooked meat. This was compounded with many chefs who added food with their hands (79%) or ate while cooking (50%). Other poor behaviors included not using a thermometer (75%), using the same cutting board to prepare ready-to-eat items and uncooked meat (25%), and other hygiene issues such as touching hair (21%) or licking fingers (21%). This study suggests that there is a need for improvement in demonstrated and communicated food safety behaviors among professional chefs. It also suggests that public health professionals must work to mitigate the impact of poorly modeled behaviors. © The Author 2016. Published by Oxford University Press on behalf of Faculty of Public Health. All rights reserved. For permissions, please e-mail: journals.permissions@oup.com.

  7. [Relevance of safety measures to avoid HTLV transmission by transfusion in 2014].

    Science.gov (United States)

    Laperche, S; Pillonel, J

    2014-11-01

    In high-income countries, the safety of blood transfusion related to viruses has reached a very high level, especially thanks to the implementation of multiple measures aimed at reducing the transfusion risk. The cost-effectiveness of these preventive measures is frequently discussed due to global financial resources, which are more and more limited. Hence, the revision of safety strategies is a key issue, especially when these strategies are redundant, as those implemented to avoid Human T-cell Lymphotropic Virus (HTLV) transmission, which are based on both antibodies screening and leucoreduction of blood products. The residual risk of the transmission of HTLV by transfusion has been recently estimated at 1 in 20 million donations (2010-2012) in France (excluding overseas territories). This estimation did not take into account the leucoreduction, which appears to be a very efficient preventive measure as the virus is strictly intra-cellular. To help decision-making, we have evaluated some parameters related to HTLV blood transmission. Firstly, the probability that an incident occurring during the leucoreduction process affects a HTLV-positive blood donation has been estimated at 1 in 178 million. Estimation of clinical consequences of HTLV-positive transfusions would affect 1 to 2 transfused-patients without leucoreduction, and one recipient every 192 years in case of 10% failures of the filtration method. Obviously, despite a risk, which appears to be controlled, HTLV screening will be disputed as soon as the efficiency of leucoreduction to totally prevent virus blood transmission will be proven and when pathogen inactivation methods are generalized to all blood cellular products. Copyright © 2014 Elsevier Masson SAS. All rights reserved.

  8. Preliminary study to questions relating to the safety of nuclear power plants A and B at Biblis

    International Nuclear Information System (INIS)

    Fischer, B.; Hahn, L.; Rausch, L.

    1985-01-01

    With a view to developing suitable tools for the safety evaluation of reactors A and B at Biblis, the publication compiles all aspects relevant to safety, creates an evaluation frame, and evaluates the aspects relevant to safety by means of this frame of evaluation. According to the composition of the work, the overall subject is split up into the complexes information, acquisition, evaluation of operational experience, probabilistic analyses, comparison with newer PWR type reactors, fulfilling of injunctions, modifications due to disposal problems, and the disposal situation. (DG) [de

  9. Food Safety at Farmers' Markets: A Knowledge Synthesis of Published Research.

    Science.gov (United States)

    Young, Ian; Thaivalappil, Abhinand; Reimer, Danielle; Greig, Judy

    2017-12-01

    Farmers' markets are increasingly popular venues in North America for the sale of fresh produce and other foods. However, the nature of their operation can present possible food safety issues, challenges, and risks to consumers. A knowledge synthesis was conducted to identify, characterize, and summarize published research on the microbial food safety issues and implications associated with farmers' markets. A scoping review was conducted using the following steps: comprehensive search strategy, relevance screening of abstracts, and characterization of relevant articles. Two subsets of data were prioritized for more detailed systematic review (data extraction and risk-of-bias assessment) and meta-analysis: (i) studies comparing the microbial safety of foods from farmers' markets versus other sources and (ii) studies evaluating the use of food safety practices at farmers' markets. Overall, 83 relevant studies were identified. The majority of studies were published as journal articles (64%), used a cross-sectional design (81%), and were conducted in the United States (78%). Most studies (39%; n = 32) investigated stakeholder, mostly consumer (n = 22), attitudes toward food safety at farmers' markets. Limited but heterogeneous evidence indicated a higher prevalence of Campylobacter and Salmonella in chicken meat from farmers' markets versus other retail sources, but there was no difference in the microbial contamination of fresh produce. Studies evaluating the use of food safety practices at farmers' markets identified some gaps; for example, the average prevalence of vendor hand washing was 4% (95% confidence interval: 0 to 11%; I 2 = 27%; n = 5 studies). Twelve foodborne outbreaks and case reports were identified, resulting in a total of 411 illnesses, 38 hospitalizations, and two deaths from 1994 to 2016. Only five intervention studies were identified. Key knowledge gaps and areas warranting future research, training, and education are highlighted and discussed.

  10. DOE/DOE Tight Oil Flammability & Transportation Spill Safety

    Energy Technology Data Exchange (ETDEWEB)

    Lord, David L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2014-12-01

    This presentation describes crude oils, their phase behavior, the SPR vapor pressure program, and presents data comparisons from various analytical techniques. The overall objective is to describe physical properties of crude oil relevant to flammability and transport safety

  11. On-going and some future safety related activities of the OECD/NEA

    International Nuclear Information System (INIS)

    Frescura, G.

    2001-01-01

    The CSNI and CNRA structures and current activities of direct relevance to WWERs are presented. The nuclear regulatory challenges arising from economic deregulation like: direct safety challenges, infrastructure issues, increased pressure on regulatory bodies etc. are given. The OECD/NEA initiatives on assuring nuclear safety competence are mentioned

  12. Do daily ward interviews improve measurement of hospital quality and safety indicators? A prospective observational study.

    Science.gov (United States)

    Sarkies, Mitchell N; Bowles, Kelly-Ann; Skinner, Elizabeth H; Haas, Romi; Mitchell, Deb; O'Brien, Lisa; May, Kerry; Ghaly, Marcelle; Ho, Melissa; Haines, Terry P

    2016-10-01

    The aim of this study was to determine if the addition of daily ward interview data improves the capture of hospital quality and safety indicators compared with incident reporting systems alone. An additional aim was to determine the potential characteristics influencing under-reporting of hospital quality and safety indicators in incident reporting systems. A prospective, observational study was performed at two tertiary metropolitan public hospitals. Research assistants from allied health backgrounds met daily with the nurse in charge of the ward and discussed the occurrence of any falls, pressure injuries and rapid response medical team calls. Data were collected from four general medical wards, four surgical wards, an orthopaedic, neurosciences, plastics, respiratory, renal, sub-acute and acute medical assessment unit. An estimated total of 303 falls, 221 pressure injuries and 884 rapid response medical team calls occurred between 15 wards across two hospitals, over a period of 6 months. Hospital incident reporting systems underestimated falls by 30.0%, pressure injuries by 59.3% and rapid response medical team calls by 17.0%. The use of ward interview data collection in addition to hospital incident reporting systems improved data capture of falls by 23.8% (n = 72), pressure injuries by 21.7% (n = 48) and rapid response medical team calls by 12.7% (n = 112). Falls events were significantly less likely to be reported if they occurred on a Monday (P = 0.04) and pressure injuries significantly more likely to be reported if they occurred on a Wednesday (P = 0.01). Hospital quality and safety indicators (falls, pressure injuries and rapid response medical team calls) were under-reported in incident reporting systems, with variability in under-reporting between wards and the day of event occurrence. The use of ward interview data collection in addition to hospital incident reporting systems improved reporting of hospital quality and safety

  13. Establishment and prioritization of relevant factors to the safety of fuel cycle facilities non reactor through dynamics archetypes evaluation

    International Nuclear Information System (INIS)

    Sousa, Anna Leticia Barbosa de

    2012-01-01

    The present work aims to establish and prioritize factors that are important to the safety of nuclear fuel cycle facilities in order to model, analyze and design safety as a physical system, employing systemic models in an innovative way. This work takes into consideration the fact that models that use adaptations of methodologies for nuclear reactors will not properly work due to the specificities of fuel cycle facilities. Based on the fundamentals of the theory of systems, the four levels of system thinking, and the relationship of eight socio technical factors, a mental model has been developed for safety management in the nuclear fuel cycle context. From this conceptual model, safety archetypes were constructed in order to identify and highlight the processes of change and decision making that allow the system to migrate to a state of loss of safety. After that, stock and flow diagrams were created so that their behavior could be assessed by the system's dynamics. The results from the analysis using the model that simulates the dynamic behavior of the variables (socio technical factors) indicated, as expected, that the system's dynamics proved to be an appropriate and efficient tool for modeling fuel cycle safety as an emergent property. (author)

  14. Large Scale Experiments on Spacecraft Fire Safety

    DEFF Research Database (Denmark)

    Urban, David L.; Ruff, Gary A.; Minster, Olivier

    2012-01-01

    -based microgravity facilities or has been limited to very small fuel samples. Still, the work conducted to date has shown that fire behaviour in low-gravity is very different from that in normal-gravity, with differences observed for flammability limits, ignition delay, flame spread behaviour, flame colour and flame......Full scale fire testing complemented by computer modelling has provided significant knowhow about the risk, prevention and suppression of fire in terrestrial systems (cars, ships, planes, buildings, mines, and tunnels). In comparison, no such testing has been carried out for manned spacecraft due...... to the complexity, cost and risk associ-ated with operating a long duration fire safety experiment of a relevant size in microgravity. Therefore, there is currently a gap in knowledge of fire behaviour in spacecraft. The entire body of low-gravity fire research has either been conducted in short duration ground...

  15. Nuclear Safety Charter

    International Nuclear Information System (INIS)

    2008-01-01

    alike, and a high level Of know-how is supported by training and skills maintenance. 3 - Transparency and reporting: Areva endeavors to provide reliable and relevant information enabling an objective assessment of the status of nuclear safety in its facilities (incident reporting, annual report of the general inspectorate, annual reporting on occupational safety during nuclear facility operations). 4 - Glossary

  16. Value-Relevance of Biological Assets under IFRS

    OpenAIRE

    Rute Gonçalves; Patrícia Lopes

    2015-01-01

    Using 389 firm-year observations of listed firms worldwide in 27 countries that adopted International Financial Reporting Standards (IFRS) until 2010, for the period 2011-2013, the purpose of this paper is to examine the value-relevance of fair value accounting of biological assets. In order to operationalize it as the book value’s ability to explain market equity value, this study adjusts the Ohlson model. The results support that recognized biological assets are value-relevant. After includ...

  17. IMP-8 observations of the spectra, composition, and variability of solar heavy ions at high energies relevant to manned space missions

    International Nuclear Information System (INIS)

    Tylka, Allan J.; Dietrich, William F.

    1999-01-01

    In more than 25 years of almost continuous observations, the University of Chicago's Cosmic Ray Telescope (CRT) on IMP-8 has amassed a unique database on high-energy solar heavy ions of potential relevance to manned spaceflight. In the very largest particle events, IMP-8/CRT has even observed solar Fe ions above the Galactic cosmic ray background up to ∼800 MeV/nucleon, an energy sufficiently high to penetrate nearly 25 g/cm 2 of shielding. IMP-8/CRT observations show that high-energy heavy-ion spectra are often surprisingly hard power laws, without the exponential roll-offs suggested by stochastic acceleration fits to lower energy measurements alone. Also, in many solar particle events the Fe/O ratio grows with increasing energy, contrary to the notion that ions with higher mass-to-charge ratios should be less abundant at higher energies. Previous studies of radiation hazards for manned spaceflight have often assumed heavy-ion composition and steeply-falling energy spectra inconsistent with these observations. Conclusions based on such studies should therefore be re-assessed. The significant event-to-event variability observed in the high-energy solar heavy ions also has important implications for strategies in building probabilistic models of solar particle radiation hazards

  18. Technology relevance of the 'uncertainty analysis in modelling' project for nuclear reactor safety

    International Nuclear Information System (INIS)

    D'Auria, F.; Langenbuch, S.; Royer, E.; Del Nevo, A.; Parisi, C.; Petruzzi, A.

    2007-01-01

    The OECD/NEA Nuclear Science Committee (NSC) endorsed the setting up of an Expert Group on Uncertainty Analysis in Modelling (UAM) in June 2006. This Expert Group reports to the Working Party on Scientific issues in Reactor Systems (WPRS) and because it addresses multi-scale / multi-physics aspects of uncertainty analysis, it will work in close co-ordination with the benchmark groups on coupled neutronics-thermal-hydraulics and on coupled core-plant problems, and the CSNI Group on Analysis and Management of Accidents (GAMA). The NEA/NSC has endorsed that this activity be undertaken with Prof. K. Ivanov from the Pennsylvania State University (PSU) as the main coordinator and host with the assistance of the Scientific Board. The objective of the proposed work is to define, coordinate, conduct, and report an international benchmark for uncertainty analysis in best-estimate coupled code calculations for design, operation, and safety analysis of LWRs entitled 'OECD UAM LWR Benchmark'. At the First Benchmark Workshop (UAM-1) held from 10 to 11 May 2007 at the OECD/NEA, one action concerned the forming of a sub-group, led by F. D'Auria, member of CSNI, responsible for defining the objectives, the impact and benefit of the UAM for safety and licensing. This report is the result of this action by the subgroup. (authors)

  19. Research on station management in subway operation safety

    Science.gov (United States)

    Li, Yiman

    2017-10-01

    The management of subway station is an important part of the safe operation of urban subway. In order to ensure the safety of subway operation, it is necessary to study the relevant factors that affect station management. In the protection of subway safety operations on the basis of improving the quality of service, to promote the sustained and healthy development of subway stations. This paper discusses the influencing factors of subway operation accident and station management, and analyzes the specific contents of station management security for subway operation, and develops effective suppression measures. It is desirable to improve the operational quality and safety factor for subway operations.

  20. Software important to safety in nuclear power plants

    International Nuclear Information System (INIS)

    1994-01-01

    The report provides guidance on current practices, documenting their strengths and weaknesses for dealing with the important issues of software engineering that nuclear power plant system designers, software producers and regulators are facing. The focus of the report is on safety critical applications of general purpose processors controlled by custom developed software; however, it should also have application in safety related applications and for other types of computers. In addition to system designers, software producers and regulators, the intended readership of this report includes users of software based systems, who should be aware of the relevant issues in specifying and obtaining software for systems important to safety. Refs, 1 fig., tabs

  1. Identification of Core Competencies for an Undergraduate Food Safety Curriculum Using a Modified Delphi Approach

    Science.gov (United States)

    Johnston, Lynette M.; Wiedmann, Martin; Orta-Ramirez, Alicia; Oliver, Haley F.; Nightingale, Kendra K.; Moore, Christina M.; Stevenson, Clinton D.; Jaykus, Lee-Ann

    2014-01-01

    Identification of core competencies for undergraduates in food safety is critical to assure courses and curricula are appropriate in maintaining a well-qualified food safety workforce. The purpose of this study was to identify and refine core competencies relevant to postsecondary food safety education using a modified Delphi method. Twenty-nine…

  2. Examples of safety culture practices

    International Nuclear Information System (INIS)

    1997-01-01

    This report has been prepared to illustrate the concepts and principles of safety culture produced in 1991 by the International Safety Advisory Group as 75-INSAG-4. It provides a small selection of examples taken from a worldwide collection of safety performance evaluations (e.g. IAEA safety series, national regulatory inspections, utility audits and a plant assessments). These documented evaluations collectively provide a database of safety performance strengths and weakness, and related safety culture observations. The examples which have been selected for inclusion in this report are those which are considered worthy of special mention and which illustrate a specific attribute of safety culture given in 75-INSAG-4

  3. [Feasibility and relevance of an operating room safety checklist for developing countries: Study in a French hospital in Djibouti].

    Science.gov (United States)

    Becret, A; Clapson, P; Andro, C; Chapelier, X; Gauthier, J; Kaiser, E

    2013-01-01

    The use of the World Health Organization surgical safety checklist, mandatory in operating rooms (OR) in France, significantly reduces morbidity and mortality. Our objective was to evaluate the use of this checklist in the OR of a French military hospital in Djibouti (Horn of Africa). The study was performed in three stages: a retrospective evaluation of the checklist use over the previous two months, to assess the utilization and completeness rates; provision of information to the OR staff; and thereafter, prospective evaluation for a one-month period of checklist use, the reasons for non-compliance, and the cases in which the checklist identified errors and thus prevented serious adverse events. The initial utilization rate was 49%, with only 24% complete. After staff training and during the study these rates reached 100% and 99%. The staff encountered language difficulties in 53% of cases, and an interpreter was available for 81% of them. The capacity of the surgical safety checklist to detect serious adverse events was highlighted. The utilization and completeness rates were initially worse than those observed in metropolitan French ORs, but a simple staff information program was rapidly effective. Language difficulties are frequent but an interpreter is often available, unlike in developed countries where language problems are uncommon and the availability of interpreters difficult. Moreover, this study illustrates the ability of the checklist to detect and therefore prevent potentially serious adverse events.

  4. Safety culture and quality management of Kartini research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Syarip [Yogyakarta Nuclear Research Centre, Yogyakarta (Indonesia); Hauptmanns, Ulrich [Department of Plant Design and Safety, Otto-Von-Guericke-University, Magdeburg (Germany)

    1999-10-01

    The evaluation for assessing the safety culture and quality of safety management of Kartini research reactor is presented. The method is based on the concept of management control of safety (audit) as well as by using the developed method i.e. the questionnaires concerning areas of relevance which have to be answered with value statements. There are seven statements or qualifiers in answering the questions. Since such statements are vague, they are represented by fuzzy numbers. The weaknesses can be identified from the different areas contemplated. The evaluation result show that the quality of safety management of Kartini research reactor is globally rated as 'Average'. The operator behavior in the implementation of 'safety culture' concept is found as a weakness, therefore this area should be improved. (author)

  5. Fuel and canister process report for the safety assessment SR-Site

    International Nuclear Information System (INIS)

    Werme, Lars; Lilja, Christina

    2010-12-01

    This report documents fuel and canister processes identified as relevant to the long-term safety of a KBS-3 repository. It forms an important part of the reporting of the safety assessment SR-Site. The detailed assessment methodology, including the role of the process reports in the assessment, is described in the SR-Site Main report /SKB 2011/

  6. Fuel and canister process report for the safety assessment SR-Site

    Energy Technology Data Exchange (ETDEWEB)

    Werme, Lars; Lilja, Christina (eds.)

    2010-12-15

    This report documents fuel and canister processes identified as relevant to the long-term safety of a KBS-3 repository. It forms an important part of the reporting of the safety assessment SR-Site. The detailed assessment methodology, including the role of the process reports in the assessment, is described in the SR-Site Main report /SKB 2011/

  7. Application of CFD Codes in Nuclear Reactor Safety Analysis

    Directory of Open Access Journals (Sweden)

    T. Höhne

    2010-01-01

    Full Text Available Computational Fluid Dynamics (CFD is increasingly being used in nuclear reactor safety (NRS analyses as a tool that enables safety relevant phenomena occurring in the reactor coolant system to be described in more detail. Numerical investigations on single phase coolant mixing in Pressurised Water Reactors (PWR have been performed at the FZD for almost a decade. The work is aimed at describing the mixing phenomena relevant for both safety analysis, particularly in steam line break and boron dilution scenarios, and mixing phenomena of interest for economical operation and the structural integrity. For the experimental investigation of horizontal two phase flows, different non pressurized channels and the TOPFLOW Hot Leg model in a pressure chamber was build and simulated with ANSYS CFX. In a common project between the University of Applied Sciences Zittau/Görlitz and FZD the behaviour of insulation material released by a LOCA released into the containment and might compromise the long term emergency cooling systems is investigated. Moreover, the actual capability of CFD is shown to contribute to fuel rod bundle design with a good CHF performance.

  8. Effectiveness of public health interventions in food safety: a systematic review.

    Science.gov (United States)

    Campbell, M E; Gardner, C E; Dwyer, J J; Isaacs, S M; Krueger, P D; Ying, J Y

    1998-01-01

    To summarize evidence on the effectiveness of public health interventions regarding food safety at restaurants, institutions, homes and other community-based settings. This systematic review of published and unpublished studies involved a comprehensive literature search, screening for relevance, quality assessment of relevant studies, data extraction and synthesis. The interventions identified in 15 studies included in this review were grouped into three categories: inspections, food handler training, and community-based education. The evidence suggests that: routine inspection (at least once per year) of food service premises is effective in reducing the risk of foodborne illness; food handler training can improve the knowledge and practices of food handlers; and selected community-based education programs can increase public knowledge of food safety. There is some evidence for the effectiveness of multiple public health interventions on food safety. Future research needs include evaluation of HACCP and community-based education programs.

  9. Visualization of Safety Assessment Result Using GIS in SITES

    International Nuclear Information System (INIS)

    Yun, Bong-Yo; Park, Joo Wan; Park, Se-Moon; Kim, Chang-Lak

    2006-01-01

    Site Information and Total Environmental database management System (SITES) is an integrated program for overall data analysis, environmental monitoring, and safety analysis that are produced from the site investigation and environmental assessment of the relevant nuclear facility. SITES is composed of three main modules such as Site Environment Characterization database for Unified and Reliable Evaluation system (SECURE), Safety Assessment INTegration system (SAINT) and Site Useful Data Analysis and ALarm system (SUDAL). The visualization function of safety assessment and environmental monitoring results is designed. This paper is to introduce the visualization design method using Geographic Information System (GIS) for SITES

  10. Principles and standards of nuclear safety and their implementation

    International Nuclear Information System (INIS)

    Franzen, L.F.

    1979-01-01

    Nuclear safety starts with the design of a nuclear facility and is only completed with its decommissioning. In the various phases of a nuclear facility's lifetime, safety evaluations are required. The licensing prerequisites for construction, operation, modification, decommissioning are based on elements of the relevant national legislation and related ordinances as well as on international regulations. They should be expanded by a system of criteria and standards spelling out the proven practice as developed over the last decades in the industrialized countries and by international organizations such IAEA with its safety codes and guides. (NEA) [fr

  11. Nuclear Energy: Compendium of relevant GAO products on regulation, health, and safety

    International Nuclear Information System (INIS)

    1986-01-01

    This report presents findings, conclusions, and recommendations in the areas of (1) protecting worker health and safety, (2) planning for nuclear emergencies and coordinating response mechanisms in the event of a serious nuclear accident, (3) ensuring the safe design of facilities, and (4) monitoring the environment. GAO points out that impaired organizational independence of the oversight function, a lack of headquarters authority, and the decentralized nature of the oversight activities may constitute serious problems over the long term. More recent GAO work indicates that organizational independence of the oversight function may still be a problem area and is likely to receive increased scrutiny in the aftermath of the Chernobyl nuclear reactor accident in the Soviet Union

  12. The Evolution of System Safety at NASA

    Science.gov (United States)

    Dezfuli, Homayoon; Everett, Chris; Groen, Frank

    2014-01-01

    The NASA system safety framework is in the process of change, motivated by the desire to promote an objectives-driven approach to system safety that explicitly focuses system safety efforts on system-level safety performance, and serves to unify, in a purposeful manner, safety-related activities that otherwise might be done in a way that results in gaps, redundancies, or unnecessary work. An objectives-driven approach to system safety affords more flexibility to determine, on a system-specific basis, the means by which adequate safety is achieved and verified. Such flexibility and efficiency is becoming increasingly important in the face of evolving engineering modalities and acquisition models, where, for example, NASA will increasingly rely on commercial providers for transportation services to low-earth orbit. A key element of this objectives-driven approach is the use of the risk-informed safety case (RISC): a structured argument, supported by a body of evidence, that provides a compelling, comprehensible and valid case that a system is or will be adequately safe for a given application in a given environment. The RISC addresses each of the objectives defined for the system, providing a rational basis for making informed risk acceptance decisions at relevant decision points in the system life cycle.

  13. Safety implications of electronic driving support systems : an orientation.

    OpenAIRE

    Gundy, C.M. Steyvers, F.J.J.M. & Kaptein, N.A.

    1995-01-01

    This report focuses on traffic safety aspects of driving support systems. The report consists of two parts. First of all, the report discusses a number of topics, relevant for the implementation and evaluation of driving support systems. These topics include: (1) safety research into driving support systems: (2) the importance of research into driver models and the driving task; (3) horizontal integration of driving support systems; (4) vertical integration of driving support systems; (5) tas...

  14. Safety Outreach and Incident Response Stakeholder Strategy

    Energy Technology Data Exchange (ETDEWEB)

    Rosewater, David Martin [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Conover, David [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-06-01

    The objective of this document is to set out a strategy to reach all stakeholders that can impact the timely deployment of safe stationary energy storage systems in the built environment with information on ESS technology and safety that is relevant to their role in deployment of the technology.

  15. Assessing progress in the development of safety culture

    International Nuclear Information System (INIS)

    Rotaru, I.; Ghita, S.; Biro, L.

    2002-01-01

    This paper is focussed on the organizational culture and learning processes required for the implementation of all aspects of safety culture. There is no prescriptive formula for improving safety culture. However, some common characteristics and practices are emerging that can be adopted by organizations in order to make progress. The paper refers to some approaches that have been successful in a number of countries. The experience of the international nuclear industry in the development and improvement of safety culture could be extended and found useful in other nuclear activities, irrespective of scale. The examples given of specific practice cover a wide range of activities including analysis of events, the regulatory approach on safety culture, employee participation and safety performance measures. Many of these practices may be relevant to smaller organizations and could contribute to improving safety culture, whatever the size of the organization. The most effective approach is to pursue a range of practices that can be mutually supportive in the development of a progressive safety culture, supported by professional standards, organizational and management commitment. Some guidance is also given on the assessment of safety culture and on the detection of a weakening safety culture. Few suggestions for accelerating the safety culture development and improvement process are also provided. (author)

  16. Exploring the role of emotional intelligence in behavior-based safety coaching.

    Science.gov (United States)

    Wiegand, Douglas M

    2007-01-01

    Safety coaching is an applied behavior analysis technique that involves interpersonal interaction to understand and manipulate environmental conditions that are directing (i.e., antecedent to) and motivating (i.e., consequences of) safety-related behavior. A safety coach must be skilled in interacting with others so as to understand their perspectives, communicate a point clearly, and be persuasive with behavior-based feedback. This article discusses the evidence-based "ability model" of emotional intelligence and its relevance to the interpersonal aspect of the safety coaching process. Emotional intelligence has potential for improving safety-related efforts and other aspects of individuals' work and personal lives. Safety researchers and practitioners are therefore encouraged to gain an understanding of emotional intelligence and conduct and support research applying this construct toward injury prevention.

  17. Safety and reliability criteria

    International Nuclear Information System (INIS)

    O'Neil, R.

    1978-01-01

    Nuclear power plants and, in particular, reactor pressure boundary components have unique reliability requirements, in that usually no significant redundancy is possible, and a single failure can give rise to possible widespread core damage and fission product release. Reliability may be required for availability or safety reasons, but in the case of the pressure boundary and certain other systems safety may dominate. Possible Safety and Reliability (S and R) criteria are proposed which would produce acceptable reactor design. Without some S and R requirement the designer has no way of knowing how far he must go in analysing his system or component, or whether his proposed solution is likely to gain acceptance. The paper shows how reliability targets for given components and systems can be individually considered against the derived S and R criteria at the design and construction stage. Since in the case of nuclear pressure boundary components there is often very little direct experience on which to base reliability studies, relevant non-nuclear experience is examined. (author)

  18. [Do residents and nurses communicate safety relevant concerns? : simulation study on the influence of the authority gradient].

    Science.gov (United States)

    St Pierre, M; Scholler, A; Strembski, D; Breuer, G

    2012-10-01

    Due to the negative impact on decision-making too steep authority gradients in teams represent a risk factor for patient safety. As residents and nursing staff may fear sanctions they may be reluctant to forward critical information to or challenge planned actions of attending physicians. In the setting of a simulation course it was investigated whether and to what extent team members would challenge decisions of familiar attending physicians. In each case where participants did not voice an opinion the underlying motives for the behavior were investigated. A total of 59 physicians and 18 nursing staff participated in the scenario. During a rapid sequence induction they were confronted with 7 critical situations created by the attending physician who had been instructed by the simulation team. Recommendations of the German Society of Anaesthesiology were ignored as well as clinical standard operating procedures (SOPs) and two potentially fatal drug administrations were ordered. An attempt was made to determine whether team members were aware of the safety threat at all and if so how they would solve the resulting conflicts. The level of verbal challenge was scored. During debriefing participants were asked to verbalize the motives which they thought might account for their silence or level of challenge. In situations where non-verbal conflict resolution was possible 65% of the participants pursued that strategy whereas 35% voiced an opinion. Situations necessitating verbal intervention were identified in 66% but 72% of the participants chose to remain silent. Team members decided to challenge the attending physician in only 28% of the situations. In 35% their statement was oblique, in 25% the problem was addressed but not further pursued and only in 40% did participants show crisp advocacy and assertiveness and initiated discussion. Asked why they had refrained from challenging the attending physician 37% had no answer, in 35% of situations participants observed a

  19. National Nuclear Safety Report 2001. Convention on Nuclear Safety

    International Nuclear Information System (INIS)

    2001-01-01

    The First National Nuclear Safety Report was presented at the first review meeting of the Nuclear Safety Convention. At that time it was concluded that Argentina met the obligations of the Convention. This second National Nuclear Safety Report is an updated report which includes all safety aspects of the Argentinian nuclear power plants and the measures taken to enhance the safety of the plants. The present report also takes into account the observations and discussions maintained during the first review meeting. The conclusion made in the first review meeting about the compliance by Argentina of the obligations of the Convention are included as Annex 1. In general, the information contained in this Report has been updated since March 31, 1998 to March 31, 2001. Those aspects that remain unchanged were not addressed in this second report with the objective of avoiding repetitions and in order to carry out a detailed analysis considering article by article. As a result of the above mentioned detailed analysis of all the Articles, it can be stated that the country fulfils all the obligations imposed by the Nuclear Safety Convention

  20. National nuclear safety report 2004. Convention on nuclear safety

    International Nuclear Information System (INIS)

    2004-01-01

    The second National Nuclear Safety Report was presented at the second review meeting of the Nuclear Safety Convention. At that time it was concluded that Argentina met the obligations of the Convention. This third National Nuclear Safety Report is an updated report which includes all safety aspects of the Argentinian nuclear power plants and the measures taken to enhance the safety of the plants. The present report also takes into account the observations and discussions maintained during the second review meeting. The conclusion made in the first review meeting about the compliance by Argentina of the obligations of the Convention are included as Annex I and those belonging to the second review meeting are included as Annex II. In general, the information contained in this Report has been updated since March 31, 2001 to April 30, 2004. Those aspects that remain unchanged were not addressed in this third report. As a result of the detailed analysis of all the Articles, it can be stated that the country fulfils all the obligations imposed by the Nuclear Safety Convention. The questions and answers originated at the Second Review Meeting are included as Annex III

  1. Improving safety in small enterprises through an integrated safety management intervention.

    Science.gov (United States)

    Kines, Pete; Andersen, Dorte; Andersen, Lars Peter; Nielsen, Kent; Pedersen, Louise

    2013-02-01

    This study tests the applicability of a participatory behavior-based injury prevention approach integrated with safety culture initiatives. Sixteen small metal industry enterprises (10-19 employees) are randomly assigned to receive the intervention or not. Safety coaching of owners/managers result in the identification of 48 safety tasks, 85% of which are solved at follow-up. Owner/manager led constructive dialogue meetings with workers result in the prioritization of 29 tasks, 79% of which are accomplished at follow-up. Intervention enterprises have significant increases on six of eight safety-perception-survey factors, while comparisons increase on only one factor. Both intervention and comparison enterprises demonstrate significant increases in their safety observation scores. Interview data validate and supplement these results, providing some evidence for behavior change and the initiation of safety culture change. Given that over 95% of enterprises in most countries have less than 20 employees, there is great potential for adapting this integrated approach to other industries. Copyright © 2012 National Safety Council and Elsevier Ltd. All rights reserved.

  2. Clinical relevance of anti-exenatide antibodies: safety, efficacy and cross-reactivity with long-term treatment

    NARCIS (Netherlands)

    Fineman, M.S.; Mace, K.F.; Diamant, M.; Darsow, T.; Cirincione, B.B.; Porter, T.K.B.; Kinninger, L.A.; Trautmann, M.E.

    2012-01-01

    Aims: Antibody formation to therapeutic peptides is common. This analysis characterizes the time-course and cross-reactivity of anti-exenatide antibodies and potential effects on efficacy and safety. Methods: Data from intent-to-treat patients in 12 controlled (n = 2225,12-52weeks) and 5

  3. ALMA observing strategies

    OpenAIRE

    Biggs, Andy

    2018-01-01

    The ALMA Observing Tool (OT) is a Java-based tool used to prepare ALMA observations. In this talk, I highlight the particular features relevant to setting up single dish observations when these are needed to observe sources where the largest angular scale requires the addition of the total power antennas.

  4. ALMA Observing Strategies

    Science.gov (United States)

    Biggs, Andy

    2018-03-01

    The ALMA Observing Tool (OT) is a Java-based tool used to prepare ALMA observations. In this talk, I highlight the particular features relevant to setting up single dish observations when these are needed to observe sources where the largest angular scale requires the addition of the total power antennas.

  5. Clinical Relevance of Nontuberculous Mycobacteria Isolated from Sputum in a Gold Mining Workforce in South Africa: An Observational, Clinical Study

    Directory of Open Access Journals (Sweden)

    Clare L. van Halsema

    2015-01-01

    Full Text Available Background. The clinical relevance of nontuberculous mycobacteria (NTM, detected by liquid more than solid culture in sputum specimens from a South African mining workforce, is uncertain. We aimed to describe the current spectrum and relevance of NTM in this population. Methods. An observational study including individuals with sputum NTM isolates, recruited at workforce tuberculosis screening and routine clinics. Symptom questionnaires were administered at the time of sputum collection and clinical records and chest radiographs reviewed retrospectively. Results. Of 232 individuals included (228 (98% male, median age 44 years, M. gordonae (60 individuals, M. kansasii (50, and M. avium complex (MAC: 38 were the commonest species. Of 38 MAC isolates, only 2 (5.3% were from smear-positive sputum specimens and 30/38 grew in liquid but not solid culture. MAC was especially prevalent among symptomatic, HIV-positive individuals. HIV prevalence was high: 57/74 (77% among those tested. No differences were found in probability of death or medical separation by NTM species. Conclusions. M. gordonae, M. kansasii, and MAC were the commonest NTM among miners with suspected tuberculosis, with most MAC from smear-negative specimens in liquid culture only. HIV testing and identification of key pathogenic NTM in this setting are essential to ensure optimal treatment.

  6. Safety aspects of nuclear power plant ageing

    International Nuclear Information System (INIS)

    1990-01-01

    The nuclear community is facing new challenges as commercial nuclear power plants (NPPs) of the first generation get older. At present, some of the plants are approaching or have even exceeded the end of their nominal design life. Experience with fossil fired power plants and in other industries shows that reliability of NPP components, and consequently general plant safety and reliability, may decline in the middle and later years of plant life. Thus, the task of maintaining operational safety and reliability during the entire plant life and especially, in its later years, is of growing importance. Recognizing the potential impact of ageing on plant safety, the IAEA convened a Working Group in 1985 to draft a report to stimulate relevant activities in the Member States. This report provided the basis for the preparation of the present document, which included a review in 1986 by a Technical Committee and the incorporation of relevant results presented at the 1987 IAEA Symposium on the Safety Aspects of the Ageing and Maintenance of NPPs and in available literature. The purpose of the present document is to increase awareness and understanding of the potential impact of ageing on plant safety; of ageing processes; and of the approach and actions needed to manage the ageing of NPP components effectively. Despite the continuing growth in knowledge on the subject during the preparation of this report it nevertheless contains much that will be of interest to a wide technical and managerial audience. Furthermore, more specific technical publications on the evaluation and management of NPP ageing and service life are being developed under the Agency's programme, which is based on the recommendations of its 1988 Advisory Group on NPP ageing. Refs, figs and tabs

  7. Current systematic carbon-cycle observations and the need for implementing a policy-relevant carbon observing system

    Science.gov (United States)

    P. Ciais; A. J. Dolman; A. Bombelli; R. Duren; A. Peregon; P. J. Rayner; C. Miller; N. Gobron; G. Kinderman; G. Marland; N. Gruber; F. Chevallier; R. J. Andres; G. Balsamo; L. Bopp; F.-M. Bréon; G. Broquet; R. Dargaville; T. J. Battin; A. Borges; H. Bovensmann; M. Buchwitz; J. Butler; J. G. Canadell; R. B. Cook; R. DeFries; R. Engelen; K. R. Gurney; C. Heinze; M. Heimann; A. Held; M. Henry; B. Law; S. Luyssaert; J. Miller; T. Moriyama; C. Moulin; R. B. Myneni; C. Nussli; M. Obersteiner; D. Ojima; Y. Pan; J.-D. Paris; S. L. Piao; B. Poulter; S. Plummer; S. Quegan; P. Raymond; M. Reichstein; L. Rivier; C. Sabine; D. Schimel; O. Tarasova; R. Valentini; R. Wang; G. van der Werf; D. Wickland; M. Williams; C. Zehner

    2014-01-01

    A globally integrated carbon observation and analysis system is needed to improve the fundamental understanding of the global carbon cycle, to improve our ability to project future changes, and to verify the effectiveness of policies aiming to reduce greenhouse gas emissions and increase carbon sequestration. Building an integrated carbon observation system requires...

  8. Nuclear safety regulation in the People's Republic of China

    International Nuclear Information System (INIS)

    Shi Guangchang

    1987-01-01

    The present report gives a general view of how the problem of nuclear safety is dealt with in China, with particular reference to the nuclear power plants. The most relevant nuclear legal regulations and procedures are reported. Organization of the National Nuclear Safety Administration (NNSA) of China and its working activities are presented. The report gives also the principle and practice with regard to licensing process and regulatory inspection of nuclear power plant in China. (author)

  9. Key practical issues in strengthening safety culture. INSAG-15. A report by the International Safety Advisory Group

    International Nuclear Information System (INIS)

    2002-01-01

    This report describes the essential practical issues to be considered by organizations aiming to strengthen safety culture. It is intended for senior executives, managers and first line supervisors in operating organizations. Although safety culture cannot be directly regulated, it is important that members of regulatory bodies understand how their actions affect the development of attempts to strengthen safety culture and are sympathetic to the need to improve the less formal human related aspects of safety. The report is therefore of relevance to regulators, although not intended primarily for them. The International Nuclear Safety Advisory Group (INSAG) introduced the concept of safety culture in its INSAG-4 report in 1991. Since then, many papers have been written on safety culture, as it relates to organizations and individuals, its improvement and its underpinning prerequisites. Variations in national cultures mean that what constitutes a good approach to enhancing safety culture in one country may not be the best approach in another. However, INSAG seeks to provide pragmatic and practical advice of wide applicability in the principles and issues presented in this report. Nuclear and radiological safety are the prime concerns of this report, but the topics discussed are so general that successful application of the principles should lead to improvements in other important areas, such as industrial safety, environmental performance and, in some respects, wider business performance. This is because many of the attitudes and practices necessary to achieve good performance in nuclear safety, including visible commitment by management, openness, care and thoroughness in completing tasks, good communication and clarity in recognizing major issues and dealing with them as a priority, have wide applicability

  10. Nuclear criticality safety training: guidelines for DOE contractors

    International Nuclear Information System (INIS)

    Crowell, M.R.

    1983-09-01

    The DOE Order 5480.1A, Chapter V, Safety of Nuclear Facilities, establishes safety procedures and requirements for DOE nuclear facilities. This guide has been developed as an aid to implementing the Chapter V requirements pertaining to nuclear criticality safety training. The guide outlines relevant conceptual knowledge and demonstrated good practices in job performance. It addresses training program operations requirements in the areas of employee evaluations, employee training records, training program evaluations, and training program records. It also suggests appropriate feedback mechanisms for criticality safety training program improvement. The emphasis is on academic rather than hands-on training. This allows a decoupling of these guidelines from specific facilities. It would be unrealistic to dictate a universal program of training because of the wide variation of operations, levels of experience, and work environments among DOE contractors and facilities. Hence, these guidelines do not address the actual implementation of a nuclear criticality safety training program, but rather they outline the general characteristics that should be included

  11. Establishing a culture for patient safety - the role of education.

    Science.gov (United States)

    Milligan, Frank J

    2007-02-01

    This paper argues that the process of making significant moves towards a patient safety culture requires changes in healthcare education. Improvements in patient safety are a shared international priority as too many errors and other forms of unnecessary harm are currently occurring in the process of caring for and treating patients. A description of the patient safety agenda is given followed by a brief analysis of human factors theory and its use in other safety critical industries, most notably aviation. The all too common problem of drug administration errors is used to illustrate the relevance of human factors theory to healthcare education with specific mention made of the Human Factors Analysis and Classification System (HFACS).

  12. Proceedings of the nuclear criticality technology safety project

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez, R.G. [comp.

    1997-06-01

    This document contains summaries of the most of the papers presented at the 1994 Nuclear Criticality Technology Safety Project (NCTSP) meeting, which was held May 10 and 11 at Williamsburg, Va. The meeting was broken up into seven sessions, which covered the following topics: (1) Validation and Application of Calculations; (2) Relevant Experiments for Criticality Safety; (3) Experimental Facilities and Capabilities; (4) Rad-Waste and Weapons Disassembly; (5) Criticality Safety Software and Development; (6) Criticality Safety Studies at Universities; and (7) Training. The minutes and list of participants of the Critical Experiment Needs Identification Workgroup meeting, which was held on May 9 at the same venue, has been included as an appendix. A second appendix contains the names and addresses of all NCTSP meeting participants. Separate abstracts have been indexed to the database for contributions to this proceedings.

  13. Proceedings of the nuclear criticality technology safety project

    International Nuclear Information System (INIS)

    Sanchez, R.G.

    1997-06-01

    This document contains summaries of the most of the papers presented at the 1994 Nuclear Criticality Technology Safety Project (NCTSP) meeting, which was held May 10 and 11 at Williamsburg, Va. The meeting was broken up into seven sessions, which covered the following topics: (1) Validation and Application of Calculations; (2) Relevant Experiments for Criticality Safety; (3) Experimental Facilities and Capabilities; (4) Rad-Waste and Weapons Disassembly; (5) Criticality Safety Software and Development; (6) Criticality Safety Studies at Universities; and (7) Training. The minutes and list of participants of the Critical Experiment Needs Identification Workgroup meeting, which was held on May 9 at the same venue, has been included as an appendix. A second appendix contains the names and addresses of all NCTSP meeting participants. Separate abstracts have been indexed to the database for contributions to this proceedings

  14. Meeting the global demand of sports safety: the intersection of science and policy in sports safety.

    Science.gov (United States)

    Timpka, Toomas; Finch, Caroline F; Goulet, Claude; Noakes, Tim; Yammine, Kaissar

    2008-01-01

    Sports and physical activity are transforming, and being transformed by, the societies in which they are practised. From the perspectives of both competitive and non-competitive sports, the complexity of their integration into today's society has led to neither sports federations nor governments being able to manage the safety problem alone. In other words, these agencies, whilst promoting sport and physical activity, deliver policy and practices in an uncoordinated way that largely ignores the need for a concurrent overall policy for sports safety. This article reviews and analyses the possibility of developing an overall sports safety policy from a global viewpoint. Firstly, we describe the role of sports in today's societies and the context within which much sport is delivered. We then discuss global issues related to injury prevention and safety in sports, with practical relevance to this important sector, including an analysis of critical policy issues necessary for the future development of the area and significant safety gains for all. We argue that there is a need to establish the sports injury problem as a critical component of general global health policy agendas, and to introduce sports safety as a mandatory component of all sustainable sports organizations. We conclude that the establishment of an explicit intersection between science and policy making is necessary for the future development of sports and the necessary safety gains required for all participants around the world. The Safe Sports International safety promotion programme is outlined as an example of an international organization active within this arena.

  15. Thermal analysis and safety information for metal nanopowders by DSC

    Energy Technology Data Exchange (ETDEWEB)

    Tseng, J.M.; Huang, S.T. [Institute of Safety and Disaster Prevention Technology, Central Taiwan University of Science and Technology, 666, Buzih Road, Beitun District, Taichung 40601, Taiwan, ROC (China); Duh, Y.S.; Hsieh, T.Y.; Sun, Y.Y. [Department of Safety Health and Environmental Engineering, National United University, Miaoli, Taiwan, ROC (China); Lin, J.Z. [Institute of Safety and Disaster Prevention Technology, Central Taiwan University of Science and Technology, 666, Buzih Road, Beitun District, Taichung 40601, Taiwan, ROC (China); Wu, H.C. [Institute of Occupational Safety and Health, Council of Labor Affairs, Taipei, Taiwan, ROC (China); Kao, C.S., E-mail: jcsk@nuu.edu.tw [Department of Safety Health and Environmental Engineering, National United University, Miaoli, Taiwan, ROC (China)

    2013-08-20

    Highlights: • Metal nanopowders are common and frequently employed in industry. • Nano iron powder experimental results of T{sub o} were 140–150 °C. • Safety information can benefit relevant metal powders industries. - Abstract: Metal nanopowders are common and frequently employed in industry. Iron is mostly applied in high-performance magnetic materials and pollutants treatment for groundwater. Zinc is widely used in brass, bronze, die casting metal, alloys, rubber, and paints, etc. Nonetheless, some disasters induced by metal powders are due to the lack of related safety information. In this study, we applied differential scanning calorimetry (DSC) and used thermal analysis software to evaluate the related thermal safety information, such as exothermic onset temperature (T{sub o}), peak of temperature (T{sub p}), and heat of reaction (ΔH). The nano iron powder experimental results of T{sub o} were 140–150 °C, 148–158 °C, and 141–149 °C for 15 nm, 35 nm, and 65 nm, respectively. The ΔH was larger than 3900 J/g, 5000 J/g, and 3900 J/g for 15 nm, 35 nm, and 65 nm, respectively. Safety information can benefit the relevant metal powders industries for preventing accidents from occurring.

  16. Safety issues and their ranking for WWER-440 model 213 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1996-04-01

    The objective of this report is to present a consolidated list of generic safety concerns, called safety issues, ranked according to their safety significance and the corrective measures to improve safety. It is intended for use as a reference to facilitate the development of plant specific safety improvement programmes and to serve as a basis for reviewing their implementation. Section 2 provides and overview of the impact of all relevant issues on the main safety functions and other aspects important to overall plant safety. Section 3 presents safety issues identified in design according to the structure described below. Section 4 presents the safety issues in the area of operation, according to the same structure except that no ranking is given. At the end of Section 2, Tables 1 and 2 present a summary of all safety issues in a tabular form. 138 refs, tabs

  17. Fracture mechanics characteristics and associated safety margins for integrity assessment; Bruchmechanische Kennwerte und zugeordnete Sicherheitsfaktoren bei Integritaetsanalysen

    Energy Technology Data Exchange (ETDEWEB)

    Roos, E.; Schuler, X.; Stumpfrock, L.; Silcher, H. [Stuttgart Univ. (DE). Materialpruefungsanstalt (MPA)

    2008-07-01

    Within the integrity assessment of components and structural members of plants safety margins have to be applied, whose magnitude depend on several factors. Important factors influencing the magnitude of the safety margins are as for instance: Material behaviour (ductile / brittle behaviour), the event to be considered (local deformation / fracture), possible consequences of failure (human health, environmental damage, economic consequences) and many others. One important factor also is the fact, how precisely and reliably the appropriate material characteristics can be determined and how precisely and reliably the components behaviour can be predicted and assessed by means of this material characteristic. In contemporary safety assessment procedures by means of fracture mechanics evaluation tools (e.g. [1]) a concept of partial safety margins is proposed for application. The basic idea with this procedure is that only those sources of uncertainty have to be considered, which are relevant or may be relevant for the structure to be considered. For this purpose each source of possible uncertainty has to be quantified individually, finally only those singular safety margins are superimposed to a total safety margin which are relevant. The more the uncertainties have to be taken into account, the total safety margin to be applied, consequently will be larger. If some sources of uncertainty can be eliminated totally or can be minimized (for instance by a more reliable calculational procedure of the component loading or by more precise material characteristics), the total safety margin can be reduced. In this contribution the different procedures for the definition of safety margins within the integrity assessment by means of fracture mechanics procedures will be discussed. (orig.)

  18. Plant safety review from mass criticality accident

    International Nuclear Information System (INIS)

    Susanto, B.G.

    2000-01-01

    The review has been done to understand the resent status of the plant in facing postulated mass criticality accident. From the design concept of the plant all the components in the system including functional groups have been designed based on favorable mass/geometry safety principle. The criticality safety for each component is guaranteed because all the dimensions relevant to criticality of the components are smaller than dimensions of 'favorable mass/geometry'. The procedures covering all aspects affecting quality including the safety related are developed and adhered to at all times. Staff are indoctrinated periodically in short training session to warn the important of the safety in process of production. The plant is fully equipped with 6 (six) criticality detectors in strategic places to alert employees whenever the postulated mass criticality accident occur. In the event of Nuclear Emergency Preparedness, PT BATAN TEKNOLOGI has also proposed the organization structure how promptly to report the crisis to Nuclear Energy Control Board (BAPETEN) Indonesia. (author)

  19. The Taskload-Efficiency-Safety-Buffer Triangle--development and validation with air traffic management.

    Science.gov (United States)

    Kallus, K Wolfgang; Hoffmann, Peter; Winkler, Hildegard; Vormayr, Elisabeth M

    2010-02-01

    The Taskload-Efficiency-Safety-Buffer Triangle (TEST) was developed as a new computerised scaling tool for quickly visualising changes in and trade-offs between the three critical factors that determine the work situation of air traffic management (ATM), i.e. taskload, efficiency and safety-buffers. Based on a task analysis of ATM and backed up by the stress-strain model, an easy-to-interpret triangle was constructed and validated both in simulated and real ATM workplaces. Results from the validation studies show that TEST does not only reflect the most relevant task characteristics, but also provides additional insights in the controllers' working styles. The TEST tool can make ATM safety surveys more efficient and help supervisors to decide about optimal times for opening or closing additional sectors. Statement of Relevance: TEST is a new tool to assess taskload, efficiency and safety-buffers in a joint scaling. It reflects increases in taskload and effects of taskload on safety-buffers and efficiency, as well as trade-offs in opposite directions. This tool might be very useful to check sector capacity in ATM and other high risk environments.

  20. Ensuring safety of people in case of severe floods: feasibility and relevance of vertical evacuation strategies in high population density areas

    Directory of Open Access Journals (Sweden)

    Pannier Rodolphe

    2016-01-01

    Full Text Available When a major flooding event is expected the authorities in charge of the crisis management often consider bringing people to safety by making them leaving temporarily the threatened area before the onset of the flood. This strategy is called “horizontal evacuation”. It has to be distinguished from “vertical evacuation”, which means that people reach a shelter above the wtaer level within the flood area. Vertical evacuation is often the spontaneousbehaviourof people who are surprised by the flood and are trying to reach a tree, a floor upstairs, a roof of a building etc. in order to get away from the rising water. But vertical evacuation could also be consideredas an alternative strategy to horizontal evacuation when moving outside the flood area is neither a faisible nor a relevant option, for example in high-population density areas. In order to be a credible alternative to horizontal evacuation, vertical evacuation has to be carefully planned. This paper aims to explain why horizontal evacuation is not always a suitable option in case of major flood and to explore under what conditions vertical evacuation can be a relevantalternative solution to horizontal evacuation. It also adresses some general recommendations about how to prepare a vertical evacuation strategy..

  1. Research on review technology for three key safety factors of periodic safety review (PSR) and its application to Qinshan Nuclear Power Plant

    International Nuclear Information System (INIS)

    Xu Shoulv; Yao Weida; Dou Yikang; Lin Shaoxuan; Cao Yenan; Zhou Quanfu; Zheng Jiong; Zhang Ming

    2009-04-01

    In 2001, after 10 years' operation, Qinshan Nuclear Power Plant (Q1) started to carry out periodic safety review (PSR) based on a nuclear safety guideline, Periodic Safety Review for Operational Nuclear Power Plants (HAF0312), issued by National Nuclear Safety Administration of China (NNSA). Entrusted by the owner of Q1, Shanghai Nuclear Engineering Research and Design Institute (SNERDI) implemented reviews of three key safety factors including safety analysis, equipment qualification and ageing. PSR was a challenging work in China at that time and through three years' research and practice, SNERDI summarized a systematic achievement for the review including review methodology, scoping, review contents and implementation steps, etc.. During the process of review for the three safety factors, totally 148 review reports and 341 recommendations for corrections were submitted to Q1. These reports and recommendations have provided guidance for correction actions as follow-up of PSR. This paper focuses on technical aspects to carry out PSR for the above-mentioned three safety factors, including review scoping, contents, methodology and main steps. The review technology and relevant experience can be taken for reference for other NPPs to carry out PSR. (authors)

  2. Sustainable safety volunteerism in the Strand, Western Cape ...

    African Journals Online (AJOL)

    There is a growing recognition of the relevance and even centrality of volunteerism to adequate collective responses to poverty, housing and the promotion of human rights and, more recently, safety. Volunteerism by members of poor global South communities within their own communities has, however, remained relatively ...

  3. Relevance as process: judgements in the context of scholarly research

    Directory of Open Access Journals (Sweden)

    Theresa D. Anderson

    2005-01-01

    Full Text Available Introduction. This paper discusses how exploring the research process in-depth and over time contributes to a fuller understanding of interactions with various representations of information. Method. A longitudinal ethnographic study explored decisions made by two informants involved in scholarly research. Relevance assessment and information seeking were observed as part of informants' own ongoing research projects. Fieldwork used methods of discovery that allowed informants to shape the exploration of the practices surrounding the evolving understandings of their topics. Analysis. Inductive analysis was carried out on the qualitative data collected over a two-year period of judgements observed on a document-by-document basis. The paper introduces broad categories that point to the variability and richness of the ways that informants used representations of information resources to make relevance judgements. Results. Relevance judgements appear to be drivers of the search and research processes informants moved through during the observations. Focusing on research goals rather than on retrieval tasks brings us to a fuller understanding of the relationship between ultimate research goals and the articulation of those goals in interactions with information systems. Conclusion. Relevance assessment is a process that unfolds in the doing of a search, the making of judgements and the using of texts and representations of information.

  4. Mitigating construction safety risks using prevention through design.

    Science.gov (United States)

    Gangolells, Marta; Casals, Miquel; Forcada, Núria; Roca, Xavier; Fuertes, Alba

    2010-04-01

    Research and practice have demonstrated that decisions made prior to work at construction sites can influence construction worker safety. However, it has also been argued that most architects and design engineers possess neither the knowledge of construction safety nor the knowledge of construction processes necessary to effectively perform Construction Hazards Prevention through Design (CHPtD). This paper introduces a quantitative methodology that supports designers by providing a way to evaluate the safety-related performance of residential construction designs using a risk analysis-based approach. The methodology compares the overall safety risk level of various construction designs and ranks the significance of the various safety risks of each of these designs. The methodology also compares the absolute importance of a particular safety risk in various construction designs. Because the methodology identifies the relevance of each safety risk at a particular site prior to the construction stage, significant risks are highlighted in advance. Thus, a range of measures for mitigating safety risks can then be implemented during on-site construction. The methodology is specially worthwhile for designers, who can compare construction techniques and systems during the design phase and determine the corresponding level of safety risk without their creative talents being restricted. By using this methodology, construction companies can improve their on-site safety performance. Copyright 2010 Elsevier Ltd. All rights reserved.

  5. Implications of safety requirements for the treatment of THMC processes in geological disposal systems for radioactive waste

    Directory of Open Access Journals (Sweden)

    Frédéric Bernier

    2017-06-01

    Full Text Available The mission of nuclear safety authorities in national radioactive waste disposal programmes is to ensure that people and the environment are protected against the hazards of ionising radiations emitted by the waste. It implies the establishment of safety requirements and the oversight of the activities of the waste management organisation in charge of implementing the programme. In Belgium, the safety requirements for geological disposal rest on the following principles: defence-in-depth, demonstrability and the radiation protection principles elaborated by the International Commission on Radiological Protection (ICRP. Applying these principles requires notably an appropriate identification and characterisation of the processes upon which the safety functions fulfilled by the disposal system rely and of the processes that may affect the system performance. Therefore, research and development (R&D on safety-relevant thermo-hydro-mechanical-chemical (THMC issues is important to build confidence in the safety assessment. This paper points out the key THMC processes that might influence radionuclide transport in a disposal system and its surrounding environment, considering the dynamic nature of these processes. Their nature and significance are expected to change according to prevailing internal and external conditions, which evolve from the repository construction phase to the whole heating–cooling cycle of decaying waste after closure. As these processes have a potential impact on safety, it is essential to identify and to understand them properly when developing a disposal concept to ensure compliance with relevant safety requirements. In particular, the investigation of THMC processes is needed to manage uncertainties. This includes the identification and characterisation of uncertainties as well as for the understanding of their safety-relevance. R&D may also be necessary to reduce uncertainties of which the magnitude does not allow

  6. Public perception of drinking water safety in South Africa 2002-2009: a repeated cross-sectional study.

    Science.gov (United States)

    Wright, Jim A; Yang, Hong; Rivett, Ulrike; Gundry, Stephen W

    2012-07-27

    In low and middle income countries, public perceptions of drinking water safety are relevant to promotion of household water treatment and to household choices over drinking water sources. However, most studies of this topic have been cross-sectional and not considered temporal variation in drinking water safety perceptions. The objective of this study is to explore trends in perceived drinking water safety in South Africa and its association with disease outbreaks, water supply and household characteristics. This repeated cross-sectional study draws on General Household Surveys from 2002-2009, a series of annual nationally representative surveys of South African households, which include a question about perceived drinking water safety. Trends in responses to this question were examined from 2002-2009 in relation to reported cholera cases. The relationship between perceived drinking water safety and organoleptic qualities of drinking water, supply characteristics, and socio-economic and demographic household characteristics was explored in 2002 and 2008 using hierarchical stepwise logistic regression. The results suggest that perceived drinking water safety has remained relatively stable over time in South Africa, once the expansion of improved supplies is controlled for. A large cholera outbreak in 2000-02 had no apparent effect on public perception of drinking water safety in 2002. Perceived drinking water safety is primarily related to water taste, odour, and clarity rather than socio-economic or demographic characteristics. This suggests that household perceptions of drinking water safety in South Africa follow similar patterns to those observed in studies in developed countries. The stability over time in public perception of drinking water safety is particularly surprising, given the large cholera outbreak that took place at the start of this period.

  7. The Chemistry of iodine in reactor safety: summary and conclusions: OECD Workshop

    International Nuclear Information System (INIS)

    1996-01-01

    About seventy experts from fourteen OECD member countries attended this Fourth OECD Workshop on the chemistry of iodine in reactor safety, as well as experts from Latvia and the Commission of the European Communities. Thirty four papers were presented, in five sessions: national and international programmes (integral and intermediate-scale experiments), experimental homogeneous phase chemistry, surface processes, thermodynamic and kinetic studies, safety applications. A final session is devoted to a general discussion on remaining research studies relevant to reactor safety

  8. Safety and Immunogenicity of a Quadrivalent Meningococcal Conjugate Vaccine and Commonly Administered Vaccines After Coadministration.

    Science.gov (United States)

    Gasparini, Roberto; Tregnaghi, Miguel; Keshavan, Pavitra; Ypma, Ellen; Han, Linda; Smolenov, Igor

    2016-01-01

    Given the broad age range across which the quadrivalent meningococcal conjugate vaccine MenACWY-CRM is used, coadministration with routine vaccines should be evaluated across age groups for possible immunologic interference and impact on vaccine reactogenicity and safety. We summarize data from a large population of infants, adolescents and international travelers from 10 phase 3 or 4 clinical studies to evaluate coadministration of MenACWY-CRM with commonly administered vaccines. Noninferiority analyses of immune responses were performed across studies and age groups for each vaccine. Reactogenicity and safety were also assessed. In infants, MenACWY-CRM coadministered with routine vaccines did not reduce immune responses to diphtheria, tetanus, poliovirus, hepatitis B, Haemophilus influenzae type b, pneumococcal conjugate, measles-mumps-rubella, varicella or pertussis antigens. Noninferiority criteria were not met for some pneumococcal conjugate serotypes at 7 months of age, but no consistent trends were observed. In adolescents, coadministration did not reduce immune responses to tetanus, diphtheria and human papilloma virus vaccine antigens. Noninferiority criteria for pertussis antigens were not uniformly met in infant and adolescent studies, although the clinical relevance is unclear. In adults, coadministration did not reduce immune responses to hepatitis A/B, typhoid fever, yellow fever, Japanese encephalitis and rabies antigens. Immune responses to MenACWY-CRM were not impacted by coadministration of commonly administered vaccines. Coadministration did not increase frequencies of postvaccination adverse events in any age group. With no clinically relevant vaccine interactions or impact on vaccine reactogenicity or safety, these results support the coadministration of MenACWY-CRM with routine vaccines in all age groups.

  9. Self-relevant beauty evaluation: Evidence from an event-related potentials study.

    Science.gov (United States)

    Kong, Fanchang; Zhang, Yan; Tian, Yuan; Fan, Cuiying; Zhou, Zongkui

    2015-03-01

    This study examines the electrophysiological correlates of beauty evaluation when participants performed the self-reference task. About 13 (7 men, 6 women) undergraduates participated in the experiment using event-related potentials. Results showed that the response to self-relevant information was faster compared to other-relevant information and no significant differences for self-relevant relative to mother-relevant information were observed. Both physical and interior beauty words for self-relevant information showed an enhanced late positive component as compared to other-relevant information. Physical beauty for self-relevant information yielded a larger late positive component in contrast to mother-relevant information but not for interior beauty. This study indicates that beauty is specific to the person who judges it though an individual and one's mother may hold similar views of interior beauty.

  10. Availability of safety relevant specialists for operation and supervision of nuclear power plants in the new EU member states; Verfuegbarkeit sicherheitsrelevanter Fachkraefte fuer Betrieb und Aufsicht von Kernkraftwerken in den EU-Mitgliedslaendern

    Energy Technology Data Exchange (ETDEWEB)

    Glaubitz, Dietmar; Dagbjartsson, Sigurdur; Wenzel, Herbert [Fichtner Management Beratung AG, Stuttgart (Germany)

    2009-07-01

    On behalf of the European commission the availability of safety relevant specialists for operation and supervision of nuclear power plants in the new EU member states was investigated. Based on information of the NPP operators and the authorities in the EU member states the authors studied the age distribution of the skilled personnel, the possibilities for long-term availability of an adequate number of experts, securing of qualification and the contribution of universities for competence preservation. Recommendations concern the cooperation of universities and NOO operators in the fields of education, training and systematic programs at the key players (training on the job).

  11. Vitamin E-drug interactions: molecular basis and clinical relevance.

    Science.gov (United States)

    Podszun, Maren; Frank, Jan

    2014-12-01

    Vitamin E (α-, β-, γ- and δ-tocopherol and -tocotrienol) is an essential factor in the human diet and regularly taken as a dietary supplement by many people, who act under the assumption that it may be good for their health and can do no harm. With the publication of meta-analyses reporting increased mortality in persons taking vitamin E supplements, the safety of the micronutrient was questioned and interactions with prescription drugs were suggested as one potentially underlying mechanism. Here, we review the evidence in the scientific literature for adverse vitamin E-drug interactions and discuss the potential of each of the eight vitamin E congeners to alter the activity of drugs. In summary, there is no evidence from animal models or randomised controlled human trials to suggest that the intake of tocopherols and tocotrienols at nutritionally relevant doses may cause adverse nutrient-drug interactions. Consumption of high-dose vitamin E supplements ( ≥  300 mg/d), however, may lead to interactions with the drugs aspirin, warfarin, tamoxifen and cyclosporine A that may alter their activities. For the majority of drugs, however, interactions with vitamin E, even at high doses, have not been observed and are thus unlikely.

  12. Contribution of psychology to the safety of installations with a high hazard potential

    International Nuclear Information System (INIS)

    Wilpert, B.

    1996-01-01

    Installations with a high hazard potential are usually characterised by the dual attribute 'low risk - high hazard'. Diverse strategies of safety management are employed in such installations in order to limit the great hazard potential of safety-relevant occurrences (faults, abnormal operating states, accidents) that can take place in them. These strategies include specific control principles. In nuclear engineering, for example, the feedforward principle has already been used for some time as a tool of analytic risk determination (e.g., in probabilistic Safety Analysis (PSA) or Human Reliability Analysis (HRA)). A further example of these strategies of safety management is the empirical determination of risks through evaluation of operating experience (feedback control, e.g., epemiological studies, accident analysis) and, derived from this, identification of the system's weak points in terms of safety. Insights derived from the application of these control principles can serve to develop specific means of intervention. These will tend to be closely oriented to the results obtained with the control method and may consist in, e.g., trainings or measures of organisation development. Independent of this, it will also be possible to identify long-term measures for preventing safety-relevant occurrences (e.g., organisational learning, safety-mindedness). The above-named strategies of safety management (control, intervention, prevention) provide a fertile basis for psychological studies in fields such as the physiology and psychology of perception (information processing), cognitive, psychology (thought and action), social psychology (division of labour, norms), paedagogic psychology (training), or organisational and environmental psychology (safety-mindedness, leadership, environmental influences). (orig./DG) [de

  13. Deep learning relevance

    DEFF Research Database (Denmark)

    Lioma, Christina; Larsen, Birger; Petersen, Casper

    2016-01-01

    train a Recurrent Neural Network (RNN) on existing relevant information to that query. We then use the RNN to "deep learn" a single, synthetic, and we assume, relevant document for that query. We design a crowdsourcing experiment to assess how relevant the "deep learned" document is, compared...... to existing relevant documents. Users are shown a query and four wordclouds (of three existing relevant documents and our deep learned synthetic document). The synthetic document is ranked on average most relevant of all....

  14. Monochloramine Cometabolism by Nitrifying Biofilm Relevant ...

    Science.gov (United States)

    Recently, biological monochloramine removal (i.e., cometabolism) by a pure culture ammonia–oxidizing bacteria, Nitrosomonas europaea, and a nitrifying mixed–culture have been shown to increase monochloramine demand. Although important, these previous suspended culture batch kinetic experiments were not representative of drinking water distribution systems where bacteria grow predominantly as biofilm attached to pipe walls or sediments and physiological differences may exist between suspension and biofilm growth. Therefore, the current research was an important next step in extending the previous results to investigate monochloramine cometabolism by biofilm grown in annular reactors under drinking water relevant conditions. Estimated monochloramine cometabolism kinetics were similar to those of ammonia metabolism, and monochloramine cometabolism was a significant loss mechanism (25–40% of the observed monochloramine loss). These results demonstrated that monochloramine cometabolism occurred in drinking water relevant nitrifying biofilm; thus, cometabolism may be a significant contribution to monochloramine loss during nitrification episodes in distribution systems. Investigate whether or not nitrifying biofilm can biologically transform monochloramine under drinking water relevant conditions.

  15. Effects of auditing patient safety in hospital care: design of a mixed-method evaluation.

    Science.gov (United States)

    Hanskamp-Sebregts, Mirelle; Zegers, Marieke; Boeijen, Wilma; Westert, Gert P; van Gurp, Petra J; Wollersheim, Hub

    2013-06-22

    Auditing of patient safety aims at early detection of risks of adverse events and is intended to encourage the continuous improvement of patient safety. The auditing should be an independent, objective assurance and consulting system. Auditing helps an organisation accomplish its objectives by bringing a systematic, disciplined approach to evaluating and improving the effectiveness of risk management, control, and governance. Audits are broadly conducted in hospitals, but little is known about their effects on the behaviour of healthcare professionals and patient safety outcomes. This study was initiated to evaluate the effects of patient safety auditing in hospital care and to explore the processes and mechanisms underlying these effects. Our study aims to evaluate an audit system to monitor and improve patient safety in a hospital setting. We are using a mixed-method evaluation with a before-and-after study design in eight departments of one university hospital in the period October 2011-July 2014. We measure several outcomes 3 months before the audit and 15 months after the audit. The primary outcomes are adverse events and complications. The secondary outcomes are experiences of patients, the standardised mortality ratio, prolonged hospital stay, patient safety culture, and team climate. We use medical record reviews, questionnaires, hospital administrative data, and observations to assess the outcomes. A process evaluation will be used to find out which components of internal auditing determine the effects. We report a study protocol of an effect and process evaluation to determine whether auditing improves patient safety in hospital care. Because auditing is a complex intervention targeted on several levels, we are using a combination of methods to collect qualitative and quantitative data about patient safety at the patient, professional, and department levels. This study is relevant for hospitals that want to early detect unsafe care and improve patient

  16. Compositional Synthesis of Safety Controllers

    NARCIS (Netherlands)

    Kuijper, W.

    2012-01-01

    In my thesis I investigate compositional techniques for synthesis of safety controllers. A safety controller, in this context, is a state machine that gives the set of safe control outputs for every possible sequence of observations from the plant under control. Compositionality, in this context,

  17. Safety culture in regulatory expert organization : analysis result of survey for KINS employees

    International Nuclear Information System (INIS)

    Choi, G. S.; Choi, Y. S.

    2003-01-01

    Much has been discussed on safety culture of operating organizations, however, little has been done on that of regulatory organization. Current issues and activities related to nuclear safety culture at IAEA, OECD/NEA, etc. were investigated and relevant literatures were reviewed. Elements essential for safety culture of regulatory organization were proposed and survey questionnaire for employees of regulatory expert organization, KINS, was developed based on the elements proposed. The survey result was presented and its implications were discussed. Based on the result, elements of safety culture in regulatory organization were proposed. The result of this survey can be used in developing safety culture model of regulatory organization, measurement method and also promotion of safety culture in regulatory organization

  18. Safety aspects in high-field magnetic resonance imaging

    International Nuclear Information System (INIS)

    Muehlenweg, M.; Trattnig, S.; Schaefers, G.

    2008-01-01

    With more and more 3 Tesla high-field magnetic resonance (MR) scanners entering clinical routine, the safety notion in MR imaging has also reached a new dimension. The first part of this paper deals with the three most important sources of physical interaction (static magnetic field, gradient and HF fields). The paper discusses the differences compared with the traditional clinical 1.5 T standard scanners, the impact on human beings, the interactions with metallic objects and the relevant safety standards. The second part of the paper examines the issue of MR safety as seen in clinical practice and tries to demonstrate optimization potentials. This includes structural optimization in information distribution and hospital organization as well as test standards and labeling guidelines. (orig.) [de

  19. Assessing medical students' perceptions of patient safety: the medical student safety attitudes and professionalism survey.

    Science.gov (United States)

    Liao, Joshua M; Etchegaray, Jason M; Williams, S Tyler; Berger, David H; Bell, Sigall K; Thomas, Eric J

    2014-02-01

    To develop and test the psychometric properties of a survey to measure students' perceptions about patient safety as observed on clinical rotations. In 2012, the authors surveyed 367 graduating fourth-year medical students at three U.S. MD-granting medical schools. They assessed the survey's reliability and construct and concurrent validity. They examined correlations between students' perceptions of organizational cultural factors, organizational patient safety measures, and students' intended safety behaviors. They also calculated percent positive scores for cultural factors. Two hundred twenty-eight students (62%) responded. Analyses identified five cultural factors (teamwork culture, safety culture, error disclosure culture, experiences with professionalism, and comfort expressing professional concerns) that had construct validity, concurrent validity, and good reliability (Cronbach alphas > 0.70). Across schools, percent positive scores for safety culture ranged from 28% (95% confidence interval [CI], 13%-43%) to 64% (30%-98%), while those for teamwork culture ranged from 47% (32%-62%) to 74% (66%-81%). They were low for error disclosure culture (range: 10% [0%-20%] to 27% [20%-35%]), experiences with professionalism (range: 7% [0%-15%] to 23% [16%-30%]), and comfort expressing professional concerns (range: 17% [5%-29%] to 38% [8%-69%]). Each cultural factor correlated positively with perceptions of overall patient safety as observed in clinical rotations (r = 0.37-0.69, P safety behavioral intent item. This study provided initial evidence for the survey's reliability and validity and illustrated its applicability for determining whether students' clinical experiences exemplify positive patient safety environments.

  20. Nuclear criticality safety evaluation of Spray Booth Operations in X-705, Portsmouth Gaseous Diffusion Plant

    International Nuclear Information System (INIS)

    Sheaffer, M.K.; Keeton, S.C.

    1993-01-01

    This report evaluates nuclear criticality safety for Spray Booth Operations in the Decontamination and Recovery Facility, X-705, at the Portsmouth Gaseous Diffusion Plant. A general description of current procedures and related hardware/equipment is presented. Control parameters relevant to nuclear criticality safety are explained, and a consolidated listing of administrative controls and safety systems is developed. Based on compliance with DOE Orders and MMES practices, the overall operation is evaluated, and recommendations for enhanced safety are suggested

  1. Laquinimod Safety Profile

    DEFF Research Database (Denmark)

    Sørensen, Per Soelberg; Comi, Giancarlo; Vollmer, Timothy L

    2017-01-01

    the safety profile of laquinimod versus placebo. Adverse events (AEs), laboratory value changes, and potential risks identified in preclinical studies were evaluated in participants in ALLEGRO and BRAVO treated with at least one dose of laquinimod or matching placebo (1:1 random assignment). RESULTS...... laquinimod studies demonstrate a safety profile comprising benign or manageable AEs and asymptomatic laboratory findings with a clear temporal pattern. Potential risks noted in preclinical studies were not observed....

  2. The specific tasks of RF TSO - FSUE VO 'Safety', related with Implementation of obligations under the Convention on Nuclear Safety

    International Nuclear Information System (INIS)

    Potapov, V.; Kuznetsov, M.; Kapralov, E.

    2010-01-01

    It was more than 20 years ago that IAEA discussed the issue pertaining to the need in scientific and engineering support to the regulatory body. The Convention on Nuclear Safety being the keystone in assurance of the global nuclear safety and security regime was adopted in 1994. It is pointed out that two independent organizations supervised by Rostechnadzor have been established within the Russian TSO system, FSUE VO 'Safety' being one of them. The tasks of the organization comprise obligatory certification of equipment as well as acceptance of equipment before its delivery to the NPP both in Russia and in the countries constructing the power units based on the Russian designs. The acceptance procedure has been set forth in the new Russian document at the level of the federal rules and regulations for nuclear safety assurance. As far as its implementation decision is concerned, a task for selection and training of personnel has been set and allocated on the Training and Methodological Center of Nuclear and Radiation Safety established with the support of FSUE VO 'Safety', which provides training programmes and specific lecture courses in the wide range of the relevant topics. (author)

  3. Education and Training of Safety Regulation for Nuclear Safety Infrastructure: Its Necessity and Unique Features

    International Nuclear Information System (INIS)

    Choi, Young Sung; Choi, Young Joon; Lee, Jae Cheon

    2009-01-01

    Faced with global warming and electricity demands, countries over the world recognize the comparative advantages of nuclear energy. It is estimated that about 300 nuclear power plants (NPPs) expect to be constructed until 2030 worldwide. In addition, according to the IAEA, approximately 20 new countries might have their first NPP in operation by 2030 in the high projection compared with bout 5 new countries in the low projection. When introducing nuclear power, the implementation of an appropriate infrastructure to address all of the relevant issues is a central concern of international community. In particular, nuclear power program requires, at an earlier stage than when construction starts, the development of a legal and regulatory framework and training of regulators and safety experts whose combined knowledge adequately covers all areas of nuclear safety and regulation applied at a NPP construction and operation. As an essential component of such human resource development, special attention was paid to the provision of education and training to regulators of which countries plan to introduce NPPs. In term of education theory, safety regulation has some unique features in learning and teaching, which are different from those of nuclear engineering or development. This paper overviews nuclear safety infrastructure, explores the roles of exporting countries, and presents features and components in education of nuclear safety regulation

  4. Confidence building in safety assessment

    International Nuclear Information System (INIS)

    Osthols, E.

    1999-01-01

    Engineered disposal systems are necessary to isolate radioactive waste from humans and the environment. It is essential to have access to basic thermochemical data relevant to varying geological environments for the radioactive elements involved. The OECD/NEA Thermochemical Data Base project (TDB) aims to make widely available basic thermochemical data of the type needed for safety assessment of nuclear storage facilities. The history and the present status of the project are presented. (K.A.)

  5. Safety-technical lay-out of the operational environment of a high-power spallation target system of the megawatt class with mercury as target material

    International Nuclear Information System (INIS)

    Butzek, M.

    2005-06-01

    This thesis is concerning the safety relevant layout of the environment of a mercury based 5-Megawatt-spallation target. All safety relevant aspects related to construction, operation and dismantling as well as economical issues were taken into account. Safety concerns are basically driven by the toxic and radioactive inventory as well as the kind and intensity of radiation produced by the spallation process. Due to significant differences in inventory and radiation between a spallation source and a fission reactor, for the design of the spallation source mentioned above the safety philosophy of a fission reactor must not be used unchanged. Rather than this a systematic study of all safety related boundary conditions is necessary. Within this thesis all safety relevant boundary conditions for this specific type of machine are given. Beside the spatial distribution of different areas inside the target station, influence of medias to be used as well as arising radiation and handling requirements are discussed in detail. A general layout of the target station is presented, serving as a basis for all further component and system development. An enclosure concept for the target station was developed, taking into account the safety relevant issues concerning the mercury used as target materials, the water cooling loops containing massive amounts of tritium as well as the materials used for the moderators potentially forming explosive mixtures. Concept and detailed technical layout of the enclosure system was chosen to guarantee safe operation of the source as well as taking care of requirement arising for handling needs. For design of the shielding different suitable materials have been discussed. A design for assembling the shielding is shown taking into account the safety relevant requirements during operation as well as during dismantling. The neutron beam shutters, buried inside the shielding were designed to optimize handling and positioning issued of the inner part

  6. Risk management for existing energy facilities. A global approach to numerical safety goals

    International Nuclear Information System (INIS)

    Pate-Cornell, M.E.

    1993-01-01

    This paper presents a structured set of numerical safety goals for risk management of existing energy facilities. The rationale behind these safety goals is based on principles of equity and economic efficiency. Some of the issues involved when using probabilistic risk analyses results for safety decisions are discussed. A brief review of existing safety targets and open-quotes floating numbersclose quotes is presented, and a set of safety goals for industrial risk management is proposed. Relaxation of these standards for existing facilities, the relevance of the lifetime of the plant, the treatment of uncertainties, and problems of failure dependencies are discussed briefly. 17 refs., 1 fig

  7. Interim process report for the safety assessment SR-Can

    International Nuclear Information System (INIS)

    Sellin, Patrick

    2004-08-01

    This report is a documentation of buffer processes identified as relevant to the long-term safety of a KBS-3 repository. The report is part of the interim reporting of the safety assessment SR-Can, see further the Interim main report. The final SR-Can reporting will support SKB's application to build an Encapsulation plant for spent nuclear fuel and is to be produced in 2006. The purpose of this report is to document the scientific knowledge of the processes to a level required for an adequate treatment in the safety assessment. The documentation is thus from a scientific point of not exhaustive since such a treatment is neither necessary for the purposes of the safety assessment nor possible within the scope of an assessment. The purpose is further to determine the handling of each process in the safety assessment and to demonstrate how uncertainties are taken care of, given the suggested handling. The process documentation in the SR 97 version of the Process report is a starting point for this SR-Can interim version. As further described in the Interim main report, the list of relevant processes has been reviewed and slightly extended by comparison to other databases. Furthermore, the backfill has been included as a system part of its own, rather than being described together with the buffer as in SR 97. Apart from giving an interim account of the documentation and handling of buffer processes in SR-Can, this report is meant to serve as a template for the forthcoming documentation of processes occurring in other parts of the repository system. A complete list of processes can be found in the Interim FEP report for the safety assessment SR-Can. All material presented in this document is preliminary in nature and will possibly be updated as the SR-Can project progresses

  8. Interim process report for the safety assessment SR-Can

    Energy Technology Data Exchange (ETDEWEB)

    Sellin, Patrick (ed.)

    2004-08-01

    This report is a documentation of buffer processes identified as relevant to the long-term safety of a KBS-3 repository. The report is part of the interim reporting of the safety assessment SR-Can, see further the Interim main report. The final SR-Can reporting will support SKB's application to build an Encapsulation plant for spent nuclear fuel and is to be produced in 2006. The purpose of this report is to document the scientific knowledge of the processes to a level required for an adequate treatment in the safety assessment. The documentation is thus from a scientific point of not exhaustive since such a treatment is neither necessary for the purposes of the safety assessment nor possible within the scope of an assessment. The purpose is further to determine the handling of each process in the safety assessment and to demonstrate how uncertainties are taken care of, given the suggested handling. The process documentation in the SR 97 version of the Process report is a starting point for this SR-Can interim version. As further described in the Interim main report, the list of relevant processes has been reviewed and slightly extended by comparison to other databases. Furthermore, the backfill has been included as a system part of its own, rather than being described together with the buffer as in SR 97. Apart from giving an interim account of the documentation and handling of buffer processes in SR-Can, this report is meant to serve as a template for the forthcoming documentation of processes occurring in other parts of the repository system. A complete list of processes can be found in the Interim FEP report for the safety assessment SR-Can. All material presented in this document is preliminary in nature and will possibly be updated as the SR-Can project progresses.

  9. Fifth national report of Brazil for the nuclear safety convention

    International Nuclear Information System (INIS)

    2010-01-01

    This Fifth National Report is a new update to include relevant information for the period of 2007/2009. This document represents the national report prepared as a fulfillment of the Brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations

  10. Safety management of an underground-based gravitational wave telescope: KAGRA

    Science.gov (United States)

    Ohishi, Naoko; Miyoki, Shinji; Uchiyama, Takashi; Miyakawa, Osamu; Ohashi, Masatake

    2014-08-01

    KAGRA is a unique gravitational wave telescope with its location underground and use of cryogenic mirrors. Safety management plays an important role for secure development and operation of such a unique and large facility. Based on relevant law in Japan, Labor Standard Act and Industrial Safety and Health Law, various countermeasures are mandated to avoid foreseeable accidents and diseases. In addition to the usual safety management of hazardous materials, such as cranes, organic solvents, lasers, there are specific safety issues in the tunnel. Prevention of collapse, flood, and fire accidents are the most critical issues for the underground facility. Ventilation is also important for prevention of air pollution by carbon monoxide, carbon dioxide, organic solvents and radon. Oxygen deficiency should also be prevented.

  11. Nuclear Safety Review for the Year 2009

    International Nuclear Information System (INIS)

    2010-07-01

    The global nuclear community is experiencing a period of dynamic change. The introduction of new nuclear power plants, the rapid expansion of existing nuclear power programmes and the wider use of radioactive sources and ionizing radiation in general highlight the need for continued and improved international cooperation to address the associated challenges. The increasingly multinational nature of today's nuclear business and activities underscores this need. In this context, it is particularly important to note that the establishment of adequate safety infrastructure and capacity cannot be left to fall behind. The safety performance of the nuclear industry has remained at a high level. Various safety performance indicators, such as those related to unplanned reactor shutdowns, safety equipment availability, radiation exposures to workers, radioactive waste management and radioactive releases to the environment have shown steady improvement over the past two decades, with some levelling off in recent years. Nevertheless, it is necessary to avoid complacency and to continuously improve and strengthen the existing global nuclear safety and security regime so that nuclear technologies can be introduced or their use expanded in a safe and secure manner to meet the world's needs for human well-being and socio-economic development. The Agency continues to support and promote increased participation in the global nuclear safety and security regime as a framework for achieving high levels of safety in nuclear activities worldwide. Through consideration of the global trends, issues and challenges observed in 2009, four key themes in global nuclear safety were identified: 1) continuing international cooperation and emerging coordination for new and expanding nuclear power programmes; 2) improving the long term management of radioactive and nuclear materials; 3) capacity building for sustainable nuclear safety; and 4) strengthening global and regional networking activities

  12. The relevance of "non-relevant metabolites" from plant protection products (PPPs) for drinking water: the German view.

    Science.gov (United States)

    Dieter, Hermann H

    2010-03-01

    "Non-relevant metabolites" are those degradation products of plant protection products (PPPs), which are devoid of the targeted toxicities of the PPP and devoid of genotoxicity. Most often, "non-relevant metabolites" have a high affinity to the aquatic environment, are very mobile within this environment, and, usually, are also persistent. Therefore, from the point of drinking water hygiene, they must be characterized as "relevant for drinking water" like many other hydrophilic/polar environmental contaminants of different origins. "Non-relevant metabolites" may therefore penetrate to water sources used for abstraction of drinking water and may thus ultimately be present in drinking water. The presence of "non-relevant metabolites" and similar trace compounds in the water cycle may endanger drinking water quality on a long-term scale. During oxidative drinking water treatment, "non-relevant metabolites" may also serve as the starting material for toxicologically relevant transformation products similar to processes observed by drinking water disinfection with chlorine. This hypothesis was recently confirmed by the detection of the formation of N-nitroso-dimethylamine from ozone and dimethylsulfamide, a "non-relevant metabolite" of the fungicide tolylfluanide. In order to keep drinking water preferably free of "non-relevant metabolites", the German drinking water advisory board of the Federal Ministry of Health supports limiting their penetration into raw and drinking water to the functionally (agriculturally) unavoidable extent. On this background, the German Federal Environment Agency (UBA) recently has recommended two health related indication values (HRIV) to assess "non-relevant metabolites" from the view of drinking water hygiene. Considering the sometimes incomplete toxicological data base for some "non-relevant metabolites", HRIV also have the role of health related precautionary values. Depending on the completeness and quality of the toxicological

  13. Safety and licensing for small and medium power reactors

    International Nuclear Information System (INIS)

    Trauger, D.B.

    1987-01-01

    Proposed new concepts for small and medium power reactors differ substantially from traditional Light Water Reactors (LWRs). Although designers have a large base of experience in safety and licensing, much of it is not relevant to new concepts. It can be a disadvantage if regulators apply LWR rules directly. A fresh start is appropriate. The extensive interactions between industry, regulators, and the public complicates but may enhance safety. It is basic to recognize the features that distinguish nuclear energy safety from that for other industries. These features include: nuclear reactivity, fission product radiation, and radioactive decay heat. Small and medium power reactors offer potential advantages over LWRs, particularly for reactivity and decay heat

  14. Safety and licensing for small and medium power reactors

    International Nuclear Information System (INIS)

    Trauger, D.B.

    1988-01-01

    Proposed new concepts for small and medium power reactors differ substantially from traditional Light Water Reactors (LWRs). Although designers have a large base of experience in safety and licensing, much of it is not relevant to new concepts. It can be a disadvantage if regulators apply LWR rules directly. A fresh start is appropriate. The extensive interactions between industry, regulators, and the public complicate but may enhance safety. It is basic to recognize the features that distinguish nuclear energy safety from that for other industries. These features include: Nuclear reactivity, fission product radiation, and radioactive decay heat. Small and medium power reactors offer potential advantages over LWRs, particularly for reactivity and decay heat. (orig.)

  15. Review of fuel safety criteria in France

    Energy Technology Data Exchange (ETDEWEB)

    Boutin, Sandrine; Graff, Stephanie; Foucher-Taisne, Aude; Dubois, Olivier [Institut de Radioprotection et du Surete Nucleaire, Fontenay-aux-Roses (France)

    2018-01-15

    Fuel safety criteria for the first barrier, based on state-of-the-art at the time, were first defined in the 1970s and came from the United States, when the French nuclear program was initiated. Since then, there has been continuous progress in knowledge and in collecting experimental results thanks to the experiments carried out by utilities and research institutes, to the operating experience, as well as to the generic R and D programs, which aim notably at improving computation methodologies, especially in Reactivity-Initiated accident and Loss-of-Coolant Accident conditions. In this context, the French utility EDF proposed new fuel safety criteria, or reviewed and completed existing safety demonstration covering the normal operating, incidental and accidental conditions of Pressurised Water Reactors. IRSN assessed EDF's proposals and presented its conclusions to the Advisory Committee for Reactors Safety of the Nuclear Safety Authority in June 2017. This review focused on the relevance of historical limit values or parameters of fuel safety criteria and their adequacy with the state-of-the-art concerning fuel physical phenomena (e.g. Pellet-Cladding Mechanical Interaction in incidental conditions, clad embrittlement due to high temperature oxidation in accidental conditions, clad ballooning and burst during boiling crisis and fuel melting).

  16. Review of fuel safety criteria in France

    International Nuclear Information System (INIS)

    Boutin, Sandrine; Graff, Stephanie; Foucher-Taisne, Aude; Dubois, Olivier

    2018-01-01

    Fuel safety criteria for the first barrier, based on state-of-the-art at the time, were first defined in the 1970s and came from the United States, when the French nuclear program was initiated. Since then, there has been continuous progress in knowledge and in collecting experimental results thanks to the experiments carried out by utilities and research institutes, to the operating experience, as well as to the generic R and D programs, which aim notably at improving computation methodologies, especially in Reactivity-Initiated accident and Loss-of-Coolant Accident conditions. In this context, the French utility EDF proposed new fuel safety criteria, or reviewed and completed existing safety demonstration covering the normal operating, incidental and accidental conditions of Pressurised Water Reactors. IRSN assessed EDF's proposals and presented its conclusions to the Advisory Committee for Reactors Safety of the Nuclear Safety Authority in June 2017. This review focused on the relevance of historical limit values or parameters of fuel safety criteria and their adequacy with the state-of-the-art concerning fuel physical phenomena (e.g. Pellet-Cladding Mechanical Interaction in incidental conditions, clad embrittlement due to high temperature oxidation in accidental conditions, clad ballooning and burst during boiling crisis and fuel melting).

  17. Recent advances in systems safety and security

    CERN Document Server

    Stamatescu, Grigore

    2016-01-01

    This book represents a timely overview of advances in systems safety and security, based on selected, revised and extended contributions from the 2nd and 3rd editions of the International Workshop on Systems Safety and Security – IWSSS, held in 2014 and 2015, respectively, in Bucharest, Romania. It includes 14 chapters, co-authored by 34 researchers from 7 countries. The book provides an useful reference from both theoretical and applied perspectives in what concerns recent progress in this area of critical interest. Contributions, broadly grouped by core topic, address challenges related to information theoretic methods for assuring systems safety and security, cloud-based solutions, image processing approaches, distributed sensor networks and legal or risk analysis viewpoints. These are mostly accompanied by associated case studies providing additional practical value and underlying the broad relevance and impact of the field.

  18. Safety Framework for Nuclear Power Source Applications in Outer Space

    International Nuclear Information System (INIS)

    2009-01-01

    space NPS are significantly different from those for terrestrial nuclear systems and are not addressed in safety guidance for terrestrial nuclear applications. After a period of initial discussion and preparation, the Scientific and Technical Subcommittee of the Committee on the Peaceful Uses of Outer Space of the United Nations and the International Atomic Energy Agency (IAEA) agreed in 2007 to jointly draft a safety framework for NPS applications in outer space. This partnership integrated the expertise of the Scientific and Technical Subcommittee in the use of space NPS with the well-established procedures of IAEA for developing safety standards pertaining to nuclear safety of terrestrial applications. The Safety Framework for Nuclear Power Source Applications in Outer Space represents a technical consensus of both bodies. The Safety Framework is intended to be utilized as a guide for national purposes. As such, it provides voluntary guidance and is not legally binding under international law. The Safety Framework is not a publication in the IAEA Safety Standards Series, but it is intended to complement the Safety Standards Series by providing high-level guidance that addresses unique nuclear safety considerations for relevant launch, operation and end-of-service mission phases of space NPS applications. It complements existing national and international safety guidance and standards pertaining to terrestrial activities that involve the design, manufacture, testing and transportation of space NPS. The Safety Framework has been developed with due consideration of relevant principles and treaties. The Safety Framework does not supplement, alter or interpret any of those principles or treaties. The focus of the Safety Framework is the protection of people and the environment in Earth's biosphere from potential hazards associated with relevant launch, operation and end-of-service mission phases of space NPS applications. The protection of humans in space is an area of

  19. Preliminary investigation on reliability assessment of passive safety system

    International Nuclear Information System (INIS)

    Huang Changfan; Kuang Bo

    2012-01-01

    The reliability evaluation of passive safety system plays an important part in probabilistic safety assessment (PSA) of nuclear power plant applying passive safety design, which depends quantitatively on reliabilities of passive safety system. According to the object of reliability assessment of passive safety system, relevant parameters are identified. Then passive system behavior during accident scenarios are studied. A practical example of this method is given for the case of reliability assessment of AP1000 passive heat removal system in loss of normal feedwater accident. Key and design parameters of PRHRS are identified and functional failure criteria are established. Parameter combinations acquired by Latin hyper~ cube sampling (LHS) in possible parametric ranges are input and calculations of uncertainty propagation through RELAP5/MOD3 code are carried out. Based on the calculations, sensitivity assessment on PRHRS functional criteria and reliability evaluation of the system are presented, which might provide further PSA with PRHR system reliability. (authors)

  20. Safety issues and their ranking for WWER-1000 model 320 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1996-03-01

    The objective of this report is to present a consolidated list of safety deficiencies, called safety issues, ranked according to their safety significance and the corrective measures to improve overall safety. It is intended for use as a reference to facilitate the development of plant specific safety improvement programmes and to serve as a basis for reviewing their implementation. To the extent that information was made available to the IAEA, the country/plant specific status with respect to each safety issue is described. Section 2 provides an overview of the impact of the relevant issues on the main safety functions in different operational conditions and other aspects important to overall plant safety. A summary of the safety issues and their respective ranking is given in Tables 1 and 2 at the end of Section 2. Section 3 deals with individual safety issues identified in the design which are presented according to the structure below. Section 4 presents the safety issues related to operational safety according to a similar structure but without the ranking. 73 refs, 3 tabs

  1. Safety issues and their ranking for WWER-1000 model 320 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1997-04-01

    The objective of this report is to present a consolidated list of safety deficiencies, called safety issues, ranked according to their safety significance and the corrective measures to improve overall safety. It is intended for use as a reference to facilitate the development of plant specific safety improvement programmes and to serve as a basis for reviewing their implementation. To the extent that information was made available to the IAEA, the country/plant specific status with respect to each safety issue is described. Section 2 provides an overview of the impact of the relevant issues on the main safety functions in different operational conditions and other aspects important to overall plant safety. A summary of the safety issues and their respective ranking is given in Tables 1 and 2 at the end of Section 2. Section 3 deals with individual safety issues identified in the design which are presented according to the structure below. Section 4 presents the safety issues related to operational safety according to a similar structure but without the ranking

  2. Applying health education theory to patient safety programs: three case studies.

    Science.gov (United States)

    Gilkey, Melissa B; Earp, Jo Anne L; French, Elizabeth A

    2008-04-01

    Program planning for patient safety is challenging because intervention-oriented surveillance data are not yet widely available to those working in this nascent field. Even so, health educators are uniquely positioned to contribute to patient safety intervention efforts because their theoretical training provides them with a guide for designing and implementing prevention programs. This article demonstrates the utility of applying health education concepts from three prominent patient safety campaigns, including the concepts of risk perception, community participation, and social marketing. The application of these theoretical concepts to patient safety programs suggests that health educators possess a knowledge base and skill set highly relevant to patient safety and that their perspective should be increasingly brought to bear on the design and evaluation of interventions that aim to protect patients from preventable medical error.

  3. Key practical issues in strengthening safety culture. INSAG-15. A report by the International Safety Advisory Group [Russian Edition

    International Nuclear Information System (INIS)

    2015-01-01

    This report describes the essential practical issues to be considered by organizations aiming to strengthen safety culture. It is intended for senior executives, managers and first line supervisors in operating organizations. Although safety culture cannot be directly regulated, it is important that members of regulatory bodies understand how their actions affect the development of attempts to strengthen safety culture and are sympathetic to the need to improve the less formal human related aspects of safety. The report is therefore of relevance to regulators, although not intended primarily for them. The International Nuclear Safety Advisory Group (INSAG) introduced the concept of safety culture in its INSAG-4 report in 1991. Since then, many papers have been written on safety culture, as it relates to organizations and individuals, its improvement and its underpinning prerequisites. Variations in national cultures mean that what constitutes a good approach to enhancing safety culture in one country may not be the best approach in another. However, INSAG seeks to provide pragmatic and practical advice of wide applicability in the principles and issues presented in this report. Nuclear and radiological safety are the prime concerns of this report, but the topics discussed are so general that successful application of the principles should lead to improvements in other important areas, such as industrial safety, environmental performance and, in some respects, wider business performance. This is because many of the attitudes and practices necessary to achieve good performance in nuclear safety, including visible commitment by management, openness, care and thoroughness in completing tasks, good communication and clarity in recognizing major issues and dealing with them as a priority, have wide applicability

  4. Recommendations and comments on the report of the Ontario Nuclear Safety Review

    International Nuclear Information System (INIS)

    1988-12-01

    The report of the Ontario Nuclear Safety Review (ONSR) prepared by Dr. F. Kenneth Hare in March 1988, is reviewed by the Advisory Committee on Nuclear Safety (ACNS) to assess for the Atomic Energy Control Board the relevance and importance of the ONSR recommendations and comments. The ACNS conclusions from this study are embodied in nineteen recommendations, as well as several suggestions and some specific comments

  5. Impacts of safety on the design of light remotely-piloted helicopter flight control systems

    International Nuclear Information System (INIS)

    Di Rito, G.; Schettini, F.

    2016-01-01

    This paper deals with the architecture definition and the safety assessment of flight control systems for light remotely-piloted helicopters for civil applications. The methods and tools to be used for these activities are standardised for conventional piloted aircraft, while they are currently a matter of discussion in case of light remotely-piloted systems flying into unsegregated airspaces. Certification concerns are particularly problematic for aerial systems weighing from 20 to 150 kgf, since the airworthiness permission is granted by national authorities. The lack of specific requirements actually requires to analyse both the existing standards for military applications and the certification guidelines for civil systems, up to derive the adequate safety objectives. In this work, after a survey on applicable certification documents for the safety objectives definition, the most relevant functional failures of a light remotely-piloted helicopter are identified and analysed via Functional Hazard Assessment. Different architectures are then compared by means of Fault-Tree Analysis, highlighting the contributions to the safety level of the main elements of the flight control system (control computers, servoactuators, antenna) and providing basic guidelines on the required redundancy level. - Highlights: • A method for architecture definition and safety assessment of light RW‐UAS flight control systems is proposed. • Relevant UAS failures are identified and analysed via Functional Hazard Assessment and Fault‐Tree Analysis. • The key safety elements are control computers, servoactuators and TX/RX system. • Single‐simplex flight control systems have inadequate safety levels. • Dual‐duplex flight control systems demonstrate to be safety compliant, with safety budgets dominated by servoactuators.

  6. Project Guarantee 1985. Final repository for high-level radioactive wastes: The system of safety barriers

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    Final disposal of radioactive waste involves preventing the waste from returning from the repository location into the biosphere by means of successively arranged containment measures known as safety barriers. In the present volume NGB 85-04 of the series of reports for Project 'Guarantee' 1985, the safety barrier system for the type C repository for high-level waste is described. The barrier parameters which are relevant for safety analysis are quantified and associated error limits and data scatter are given. The aim of the report is to give a summary documentation of the safety analysis input data and their scientific background. For secure containment of radioactive waste safety barriers are used which effectively limit the release of radioactive material from the repository (release barriers) and effectively retard the entry of the original radioactive material into the biosphere (time barriers). Safety barriers take the form of both technically constructed containment measures and the siting of the repository in suitable geological formations. The technical safety barrier system in the case of high-level waste comprises: the waste solidification matrix (borosilicate glass), massive steel canisters, encasement of the waste canisters, encasement of the waste canisters in highly compacted bentonite, sealing of vacant storage space and access routes on repository closure. The natural geological safety barriers - the host rock and overlying formations provide sufficiently long deep groundwater flow times from the repository location to the earth's surface and for additional lengthening of radionuclide migration times by means of various chemical and physical retardation mechanisms. The stability of the geological formations is so great that hydrogeological system is protected for a sufficient length of time from deterioration caused, in particular, by erosion. Observations in the final section of the report indicate that input data for the type C repository safety

  7. Improving patient safety during insertion of peripheral venous catheters: an observational intervention study

    Directory of Open Access Journals (Sweden)

    Kampf, Günter

    2013-11-01

    Full Text Available [english] Background: Peripheral venous catheters are frequently used in hospitalized patients but increase the risk of nosocomial bloodstream infection. Evidence-based guidelines describe specific steps that are known to reduce infection risk. However, the degree of guideline implementation in clinical practice is not known. The aim of this study was to determine the use of specific steps for insertion of peripheral venous catheters in clinical practice and to implement a multimodal intervention aimed at improving both compliance and the optimum order of the steps.Methods: The study was conducted at University Hospital Hamburg. An optimum procedure for inserting a peripheral venous catheter was defined based on three evidence-based guidelines (WHO, CDC, RKI including five steps with 1A or 1B level of evidence: hand disinfection before patient contact, skin antisepsis of the puncture site, no palpation of treated puncture site, hand disinfection before aseptic procedure, and sterile dressing on the puncture site. A research nurse observed and recorded procedures for peripheral venous catheter insertion for healthcare workers in four different departments (endoscopy, central emergency admissions, pediatrics, and dermatology. A multimodal intervention with 5 elements was established (teaching session, dummy training, e-learning tool, tablet and poster, and direct feedback, followed by a second observation period. During the last observation week, participants evaluated the intervention.Results: In the control period, 207 insertions were observed, and 202 in the intervention period. Compliance improved significantly for four of five steps (e.g., from 11.6% to 57.9% for hand disinfection before patient contact; p<0.001, chi-square test. Compliance with skin antisepsis of the puncture site was high before and after intervention (99.5% before and 99.0% after. Performance of specific steps in the correct order also improved (e.g., from 7.7% to 68

  8. Data report for the safety assessment SR-Site

    International Nuclear Information System (INIS)

    2010-12-01

    This report compiles, documents, and qualifies input data identified as essential for the long-term safety assessment of a KBS-3 repository, and forms an important part of the reporting of the safety assessment project SR-Site. The input data concern the repository system, broadly defined as the deposited spent nuclear fuel, the engineered barriers surrounding it, the host rock, and the biosphere in the proximity of the repository. The input data also concern external influences acting on the system, in terms of climate related data. Data are provided for a selection of relevant conditions and are qualified through traceable standardised procedures

  9. Data report for the safety assessment SR-Site

    Energy Technology Data Exchange (ETDEWEB)

    2010-12-15

    This report compiles, documents, and qualifies input data identified as essential for the long-term safety assessment of a KBS-3 repository, and forms an important part of the reporting of the safety assessment project SR-Site. The input data concern the repository system, broadly defined as the deposited spent nuclear fuel, the engineered barriers surrounding it, the host rock, and the biosphere in the proximity of the repository. The input data also concern external influences acting on the system, in terms of climate related data. Data are provided for a selection of relevant conditions and are qualified through traceable standardised procedures

  10. Safety and efficacy of fenproporex for obesity treatment: a systematic review

    OpenAIRE

    Paumgartten,Francisco José Roma; Pereira,Sabrina Schaaf Teixeira Costa; Oliveira,Ana Cecilia Amado Xavier de

    2016-01-01

    ABSTRACT OBJECTIVE To evaluate clinical evidence on the safety and efficacy of fenproporex for treating obesity. METHODS MEDLINE, LILACS and Cochrane Controlled Trials Register were searched as well as references cited by articles and relevant documents. Two authors independently assessed the studies for inclusion and regarding risk of bias, collected data, and accuracy. Eligible studies were all those placebo-controlled that provided data on the efficacy and safety of Fenproporex to trea...

  11. Measuring safety climate in elderly homes.

    Science.gov (United States)

    Yeung, Koon-Chuen; Chan, Charles C

    2012-02-01

    Provision of a valid and reliable safety climate dimension brings enormous benefits to the elderly home sector. The aim of the present study was to make use of the safety climate instrument developed by OSHC to measure the safety perceptions of employees in elderly homes such that the factor structure of the safety climate dimensions of elderly homes could be explored. In 2010, surveys by mustering on site method were administered in 27 elderly homes that had participated in the "Hong Kong Safe and Healthy Residential Care Home Accreditation Scheme" organized by the Occupational Safety and Health Council. Six hundred and fifty-one surveys were returned with a response rate of 54.3%. To examine the factor structure of safety climate dimensions in our study, an exploratory factor analysis (EFA) using principal components analysis method was conducted to identify the underlying factors. The results of the modified seven-factor's safety climate structure extracted from 35 items better reflected the safety climate dimensions of elderly homes. The Cronbach alpha range for this study (0.655 to 0.851) indicated good internal consistency among the seven-factor structure. Responses from managerial level, supervisory and professional level, and front-line staff were analyzed to come up with the suggestion on effective ways of improving the safety culture of elderly homes. The overall results showed that managers generally gave positive responses in the factors evaluated, such as "management commitment and concern to safety," "perception of work risks and some contributory influences," "safety communication and awareness," and "safe working attitude and participation." Supervisors / professionals, and frontline level staff on the other hand, have less positive responses. The result of the lowest score in the factors - "perception of safety rules and procedures" underlined the importance of the relevance and practicability of safety rules and procedures. The modified OSHC

  12. Pearl Harbor: lessons for the dam safety community

    Energy Technology Data Exchange (ETDEWEB)

    Martin, T.E. [AMEC Earth and Environmental Ltd., Burnaby, BC (Canada)

    2001-10-01

    Every good dam safety program must be based on surveillance and emergency response planning. The same principles apply to the gathering of information for military intelligence and the planning of defence tactics. Lessons learned from failure have spurred the advancement of dam engineering. Dam safety experts can benefit from the inadequacies encountered by the military community, with the most famous occurring on December 7, 1941 in Pearl Harbor. Both intelligence gathering and contingency response planning failed miserably. The data was not properly disseminated, interpreted, analysed. The proper response to the situation was not initiated. Human error and failure to communicate are the two main reasons that explain the debacle. The inquiries into the tragedy at Pearl Harbor provided valuable lessons, related to individual and organizational failures, which the authors shared in this presentation. The relevance to dam safety was made. All Federal Bureau of Investigation (FBI) agents must read the lessons drawn from Pearl Harbor, as they have responsibility for dam safety. 4 refs.

  13. Some considerations on the safety of nuclear ships

    International Nuclear Information System (INIS)

    Kuramoto, Masaaki

    1978-01-01

    For realizing the practical utilization of nuclear merchant ships, it is essential to gain their acceptance by maritime countries on an equal footing with conventional vessels, and to have the administrative procedures for their admission simplified. This, however cannot be expected to be attained overnight, and progressive measures will have to be adopted, to approach the ultimate goal step by step. The first step should be to demonstrate the safety of nuclear propulsion, for which nuclear ships must accumulate their mileages of safe service. The second important step is to simplify the procedures demanded of nuclear ships for access to ports, through the establishment of international safety standards and design criteria, the enforcement of safety measures covering the entrance of nuclear ships into ports, and the assurance of safety in he repair, inspection and refuelling operations of these ships. Among these measures, the considerations relevant to port entry are the subject of vital interest to both ship operators and port authorities

  14. Efficacy and safety of the partial PPARγ agonist balaglitazone compared with pioglitazone and placebo: A phase III, randomised, parallel-group study in patients with type 2 diabetes on stable insulin therapy

    DEFF Research Database (Denmark)

    Henriksen, Kim; Byrjalsen, Inger; Qvist, Per

    2011-01-01

    Treatment of patients with full PPARγ agonists is associated with weight gain, heart failure, peripheral oedema and bone loss. However, the safety of partial PPARγ agonists has not been established in a clinical trial. The BALLET trial aimed to establish the glucose-lowering effects and safety...... in all treatment arms. DXA analyses showed balaglitazone 10mg led to less fat and fluid accumulation and no change in bone mineral density, when compared to pioglitazone. In the balaglitazone 10mg treated group clinically relevant reductions in HbA(1c) and glucose levels were observed, although...... it appeared to be a little less potent that pioglitazone 45mg. On the other hand significantly less fluid and fat accumulation were observed, highlighting this treatment regimen for further studies....

  15. Developing an OMERACT Core Outcome Set for Assessing Safety Components in Rheumatology Trials: The OMERACT Safety Working Group.

    Science.gov (United States)

    Klokker, Louise; Tugwell, Peter; Furst, Daniel E; Devoe, Dan; Williamson, Paula; Terwee, Caroline B; Suarez-Almazor, Maria E; Strand, Vibeke; Woodworth, Thasia; Leong, Amye L; Goel, Niti; Boers, Maarten; Brooks, Peter M; Simon, Lee S; Christensen, Robin

    2017-12-01

    Failure to report harmful outcomes in clinical research can introduce bias favoring a potentially harmful intervention. While core outcome sets (COS) are available for benefits in randomized controlled trials in many rheumatic conditions, less attention has been paid to safety in such COS. The Outcome Measures in Rheumatology (OMERACT) Filter 2.0 emphasizes the importance of measuring harms. The Safety Working Group was reestablished at the OMERACT 2016 with the objective to develop a COS for assessing safety components in trials across rheumatologic conditions. The safety issue has previously been discussed at OMERACT, but without a consistent approach to ensure harms were included in COS. Our methods include (1) identifying harmful outcomes in trials of interventions studied in patients with rheumatic diseases by a systematic literature review, (2) identifying components of safety that should be measured in such trials by use of a patient-driven approach including qualitative data collection and statistical organization of data, and (3) developing a COS through consensus processes including everyone involved. Members of OMERACT including patients, clinicians, researchers, methodologists, and industry representatives reached consensus on the need to continue the efforts on developing a COS for safety in rheumatology trials. There was a general agreement about the need to identify safety-related outcomes that are meaningful to patients, framed in terms that patients consider relevant so that they will be able to make informed decisions. The OMERACT Safety Working Group will advance the work previously done within OMERACT using a new patient-driven approach.

  16. Best Estimate plus Uncertainty (BEPU) Analyses in the IAEA Safety Standards

    International Nuclear Information System (INIS)

    Dusic, Milorad; )

    2013-01-01

    The Safety Standards Series establishes an essential basis for safety and represents the broadest international consensus. Safety Standards Series publications are categorized into: Safety Fundamental (Present the overall objectives, concepts and principles of protection and safety, they are the policy documents of the safety standards), Safety Requirements (Establish requirements that must be met to ensure the protection and safety of people and the environment, both now and in the future), and Safety Guides (Provide guidance, in the form of more detailed actions, conditions or procedures that can be used to comply with the Requirements). The incorporation of more detailed requirements, in accordance with national practice, may still be necessary. There should be only one set of international safety standards. Each safety standard will be reviewed by the relevant committee or by the commission every five years. Best Estimate plus Uncertainty (BEPU) Analyses are approached in the following IAEA Safety Standards: - Safety Requirements SSR 2/1 - Safety of NPPs, Design (Revision of NS-R-1); - General Safety Requirement GSR Part 4: Safety Assessment for Facilities and Activities; - Safety Guide SSG-2 Deterministic Safety Analysis for Nuclear Power Plants. NUSSC suggested that new safety guides should be accompanied by documents like TECDOCs or Safety Reports describing in detail their recommendations where appropriate. Special review is currently underway to identify needs for revision in the light of the Fukushima accident. Revision will concern, first, the Safety Requirements, and then, the Selected Safety Guides

  17. A preliminary study on the design in architecture of nuclear and radiation safety standard system

    International Nuclear Information System (INIS)

    Song Dahu; Zhang Chi; Yang Lili; Li Bin; Liu Yingwei; An Hongzhen; Gao Siyi; Liu Ting; Meng De

    2014-01-01

    The connotation and function of nuclear and radiation safety standards are analyzed, and their relationships with the relevant laws and regulations are discussed in the paper. Some suggestions and blue print of overall architecture to build nuclear and radiation safety standard system are proposed, on the basis of researching the application status quo, existing problems and needs for nuclear and radiation safety standards in China. This work is a beneficial exploration and attempt to establish China's nuclear and radiation safety standards. (authors)

  18. The development of international safety standards on geological disposal

    International Nuclear Information System (INIS)

    McCartin, T.

    2005-01-01

    The IAEA is developing a set of safety requirements for geologic disposal to be used by both developers and regulators for planning, designing, operating, and closing a geologic disposal facility. Safety requirements would include quantitative criteria for assessing safety of geologic disposal facilities as well as requirements for development of the facility and the safety strategy including the safety case. Geologic disposal facilities are anticipated to be developed over a period of at least a few decades. Key decisions, e.g., on the disposal concept, siting, design, operational management and closure, are expected to be made in a series of steps. Decisions will be made based on the information available at each step and the confidence that may be placed in that information. A safety strategy is important for ensuring that at each step during the development of the disposal facility, an adequate understanding of the safety implications of the available options is developed such that the ultimate goal of providing an acceptable level of operational and post closure safety will be met. A safety case for a geologic disposal facility would present all the safety relevant aspects of the site, the facility design and the managerial and regulatory controls. The safety case and its supporting assessments illustrates the level of protection provided and shall give reasonable assurance that safety standards will be met. Overall, the safety case provides confidence in the feasibility of implementing the disposal system as designed, convincing estimates of the performance of the disposal system and a reasonable assurance that safety standards will be met. (author)

  19. Taking up national safety alerts to improve patient safety in hospitals: The perspective of healthcare quality and risk managers.

    Science.gov (United States)

    Pfeiffer, Yvonne; Schwappach, David

    2016-01-01

    National safety alert systems publish relevant information to improve patient safety in hospitals. However, the information has to be transformed into local action to have an effect on patient safety. We studied three research questions: How do Swiss healthcare quality and risk managers (qm/rm(1)) see their own role in learning from safety alerts issued by the Swiss national voluntary reporting and analysis system? What are their attitudes towards and evaluations of the alerts, and which types of improvement actions were fostered by the safety alerts? A survey was developed and applied to Swiss healthcare risk and quality managers, with a response rate of 39 % (n=116). Descriptive statistics are presented. The qm/rm disseminate and communicate with a broad variety of professional groups about the alerts. While most respondents felt that they should know the alerts and their contents, only a part of them felt responsible for driving organizational change based on the recommendations. However, most respondents used safety alerts to back up their own patient safety goals. The alerts were evaluated positively on various dimensions such as usefulness and were considered as standards of good practice by the majority of the respondents. A range of organizational responses was applied, with disseminating information being the most common. An active role is related to using safety alerts for backing up own patient safety goals. To support an active role of qm/rm in their hospital's learning from safety alerts, appropriate organizational structures should be developed. Furthermore, they could be given special information or training to act as an information hub on the issues discussed in the alerts. Copyright © 2016. Published by Elsevier GmbH.

  20. Research study about the establishment of safety culture. Effects of organizational factors in construction industry's safety indices

    International Nuclear Information System (INIS)

    Kojima, Mitsuhiro; Hirose, Humiko; Takano, Kenichi; Hasegawa, Naoko

    1999-01-01

    To find the relationships between safety related activities (such as safety patrol' or '4s/5s activities') and accidents rate in the workplace, questionnaires were sent to 965 construction companies and 120 answers were returned. In this questionnaire, safety activities, safety regulations and safety policies of the companies were asked and organizational climates, company policies, philosophies and the number of accidents in workplace were also asked. There seems some relationships between accidents rate and safety activities, safety regulations and safety policies in the companies, but the deviations between estimate values and observed values are so great that it seems impossible to estimate the accidents rate in the working place from the safety activities, safety regulations and safety policies of the companies. On the other hand, some characteristics of safety activities and organizational climates in the construction industry were identified using multi variants analysis. More detailed researches using sophisticated questionnaire will be conducted in the construction industry and petrochemical industry and relationships between the accidents rate and the safety activities will be compared between different industries. (author)

  1. Nuclear Safety Review for 2015

    International Nuclear Information System (INIS)

    2015-06-01

    The Nuclear Safety Review 2015 focuses on the dominant nuclear safety trends, issues and challenges in 2014. The Executive Overview provides general nuclear safety information along with a summary of the major issues covered in this report: improving radiation, transport and waste safety; strengthening safety in nuclear installations; enhancing emergency preparedness and response (EPR); and strengthening civil liability for nuclear damage. The Appendix provides details on the activities of the Commission on Safety Standards (CSS), and activities relevant to the Agency’s safety standards. The global nuclear community continued to make steady progress in improving nuclear safety throughout the world in 2014; and, the Agency and its Member States continued to implement the IAEA Action Plan on Nuclear Safety (hereinafter referred to as “the Action Plan”), which was endorsed by the General Conference in 2011 after the Fukushima Daiichi accident in March 2011. • Significant progress has been made in reviewing and revising various Agency’s safety standards in areas such as management of radioactive waste, design basis hazard levels, protection of nuclear power plants (NPPs) against severe accidents, design margins to avoid cliff edge effects, multiple facilities at one site, and strengthening the prevention of unacceptable radiological consequences to the public and the environment, communications and EPR. In addition, the Guidelines for Drafting IAEA Safety Standards and Nuclear Security Series Publications was issued in July 2014.• The Agency continued to analyse the relevant technical aspects of the Fukushima Daiichi accident and to share and disseminate lessons learned to the wider nuclear community. In 2014, the Agency organized two international experts’ meetings (IEMs), one on radiation protection and one on severe accident management. Reports from previous IEMs were also published in 2014: IAEA Report on Human and Organizational Factors in Nuclear

  2. INFO ANAV, a channel that is consolidated in the communication of information relevant to plant safety

    International Nuclear Information System (INIS)

    Lopera Broto, A. J.; Balbas Gomez, S.

    2012-01-01

    This weekly publication intended to make it to all the people who work at the sites of Asco and Vandellos relevant information for security since we are all responsible for the safe and reliable operation of our plants.

  3. Nuclear safety research collaborations between the U.S. and Russian Federation International Nuclear Safety Centers

    International Nuclear Information System (INIS)

    Hill, D. J.; Braun, J. C.; Klickman, A. E.; Bougaenko, S. E.; Kabonov, L. P.; Kraev, A. G.

    2000-01-01

    The Russian Federation Ministry for Atomic Energy (MINATOM) and the US Department of Energy (USDOE) have formed International Nuclear Safety Centers to collaborate on nuclear safety research. USDOE established the US Center (ISINSC) at Argonne National Laboratory (ANL) in October 1995. MINATOM established the Russian Center (RINSC) at the Research and Development Institute of Power Engineering (RDIPE) in Moscow in July 1996. In April 1998 the Russian center became a semi-independent, autonomous organization under MINATOM. The goals of the center are to: Cooperate in the development of technologies associated with nuclear safety in nuclear power engineering; Be international centers for the collection of information important for safety and technical improvements in nuclear power engineering; and Maintain a base for fundamental knowledge needed to design nuclear reactors. The strategic approach is being used to accomplish these goals is for the two centers to work together to use the resources and the talents of the scientists associated with the US Center and the Russian Center to do collaborative research to improve the safety of Russian-designed nuclear reactors. The two centers started conducting joint research and development projects in January 1997. Since that time the following ten joint projects have been initiated: INSC databases--web server and computing center; Coupled codes--Neutronic and thermal-hydraulic; Severe accident management for Soviet-designed reactors; Transient management and advanced control; Survey of relevant nuclear safety research facilities in the Russian Federation; Computer code validation for transient analysis of VVER and RBMK reactors; Advanced structural analysis; Development of a nuclear safety research and development plan for MINATOM; Properties and applications of heavy liquid metal coolants; and Material properties measurement and assessment. Currently, there is activity in eight of these projects. Details on each of these

  4. An integrative review of patient safety in studies on the care and safety of patients with communication disabilities in hospital.

    Science.gov (United States)

    Hemsley, Bronwyn; Georgiou, Andrew; Hill, Sophie; Rollo, Megan; Steel, Joanne; Balandin, Susan

    2016-04-01

    To review the research literature on the experiences of patients with communication disabilities in hospital according to the Generic Model of patient safety. In 2014 and 2015, we searched four scientific databases for studies with an aim or result relevant to safety of hospital patients with communication disabilities. The review included 27 studies. A range of adverse event types were outlined in qualitative research. Little detail was provided about contributing or protective factors for safety incidents in hospital for these patients or the impact of the incidents on the patient or organisations involved. Further research addressing the safety of patients with communication disabilities is needed. Sufficient detail is required to identify the nature, timing, and detection of incidents; factors that contribute to or prevent adverse events; and detail the impact of the adverse events. In order to provide safe and effective care to people with communication disabilities in hospital, a priority for health and disability services must be the design and evaluation of ecologically appropriate and evidence-based interventions to improve patient care, communication, and reduce the risk of costly and harmful patient safety incidents. Copyright © 2015 Elsevier Ireland Ltd. All rights reserved.

  5. The experience of WNTI with Safety and Security Worldwide

    International Nuclear Information System (INIS)

    Neau, Henry-Jacques

    2016-01-01

    This paper gives an industrial perspective on safety and security issues based on the experience of WNTI members. It describes how safety is invested primarily in the package; not how the package is transported. Transport safety is therefore an engineering challenge, and all necessary technical information is available to enable this to be met. Security in transport involves various measures to guard against intentional malicious acts. The paper describes the international instruments relevant to security in the transport of nuclear fuel cycle materials and how both safety and security regulations must be coordinated and simplified to avoid conflicts. It considers potential risks, which must not be underestimated. However, the assessment of risks must be realistic and quantified, and the requirements placed on the industry appropriate. It is important to dispel exaggerated perceptions of danger in the minds of the public, politicians and regulators. (author)

  6. Software for computer based systems important to safety in nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2004-01-01

    Computer based systems are of increasing importance to safety in nuclear power plants as their use in both new and older plants is rapidly increasing. They are used both in safety related applications, such as some functions of the process control and monitoring systems, as well as in safety critical applications, such as reactor protection or actuation of safety features. The dependability of computer based systems important to safety is therefore of prime interest and should be ensured. With current technology, it is possible in principle to develop computer based instrumentation and control systems for systems important to safety that have the potential for improving the level of safety and reliability with sufficient dependability. However, their dependability can be predicted and demonstrated only if a systematic, fully documented and reviewable engineering process is followed. Although a number of national and international standards dealing with quality assurance for computer based systems important to safety have been or are being prepared, internationally agreed criteria for demonstrating the safety of such systems are not generally available. It is recognized that there may be other ways of providing the necessary safety demonstration than those recommended here. The basic requirements for the design of safety systems for nuclear power plants are provided in the Requirements for Design issued in the IAEA Safety Standards Series.The IAEA has issued a Technical Report to assist Member States in ensuring that computer based systems important to safety in nuclear power plants are safe and properly licensed. The report provides information on current software engineering practices and, together with relevant standards, forms a technical basis for this Safety Guide. The objective of this Safety Guide is to provide guidance on the collection of evidence and preparation of documentation to be used in the safety demonstration for the software for computer based

  7. Software for computer based systems important to safety in nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2005-01-01

    Computer based systems are of increasing importance to safety in nuclear power plants as their use in both new and older plants is rapidly increasing. They are used both in safety related applications, such as some functions of the process control and monitoring systems, as well as in safety critical applications, such as reactor protection or actuation of safety features. The dependability of computer based systems important to safety is therefore of prime interest and should be ensured. With current technology, it is possible in principle to develop computer based instrumentation and control systems for systems important to safety that have the potential for improving the level of safety and reliability with sufficient dependability. However, their dependability can be predicted and demonstrated only if a systematic, fully documented and reviewable engineering process is followed. Although a number of national and international standards dealing with quality assurance for computer based systems important to safety have been or are being prepared, internationally agreed criteria for demonstrating the safety of such systems are not generally available. It is recognized that there may be other ways of providing the necessary safety demonstration than those recommended here. The basic requirements for the design of safety systems for nuclear power plants are provided in the Requirements for Design issued in the IAEA Safety Standards Series.The IAEA has issued a Technical Report to assist Member States in ensuring that computer based systems important to safety in nuclear power plants are safe and properly licensed. The report provides information on current software engineering practices and, together with relevant standards, forms a technical basis for this Safety Guide. The objective of this Safety Guide is to provide guidance on the collection of evidence and preparation of documentation to be used in the safety demonstration for the software for computer based

  8. Software for computer based systems important to safety in nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2000-01-01

    Computer based systems are of increasing importance to safety in nuclear power plants as their use in both new and older plants is rapidly increasing. They are used both in safety related applications, such as some functions of the process control and monitoring systems, as well as in safety critical applications, such as reactor protection or actuation of safety features. The dependability of computer based systems important to safety is therefore of prime interest and should be ensured. With current technology, it is possible in principle to develop computer based instrumentation and control systems for systems important to safety that have the potential for improving the level of safety and reliability with sufficient dependability. However, their dependability can be predicted and demonstrated only if a systematic, fully documented and reviewable engineering process is followed. Although a number of national and international standards dealing with quality assurance for computer based systems important to safety have been or are being prepared, internationally agreed criteria for demonstrating the safety of such systems are not generally available. It is recognized that there may be other ways of providing the necessary safety demonstration than those recommended here. The basic requirements for the design of safety systems for nuclear power plants are provided in the Requirements for Design issued in the IAEA Safety Standards Series.The IAEA has issued a Technical Report to assist Member States in ensuring that computer based systems important to safety in nuclear power plants are safe and properly licensed. The report provides information on current software engineering practices and, together with relevant standards, forms a technical basis for this Safety Guide. The objective of this Safety Guide is to provide guidance on the collection of evidence and preparation of documentation to be used in the safety demonstration for the software for computer based

  9. Quality assurance for software important to safety

    International Nuclear Information System (INIS)

    2000-01-01

    Software applications play an increasingly relevant role in nuclear power plant systems. This is particularly true of software important to safety used in both: calculations for the design, testing and analysis of nuclear reactor systems (design, engineering and analysis software); and monitoring, control and safety functions as an integral part of the reactor systems (monitoring, control and safety system software). Computer technology is advancing at a fast pace, offering new possibilities in nuclear reactor design, construction, commissioning, operation, maintenance and decommissioning. These advances also present new issues which must be considered both by the utility and by the regulatory organization. Refurbishment of ageing instrumentation and control systems in nuclear power plants and new safety related application areas have emerged, with direct (e.g. interfaces with safety systems) and indirect (e.g. operator intervention) implications for safety. Currently, there exist several international standards and guides on quality assurance for software important to safety. However, none of the existing documents provides comprehensive guidance to the developer, manager and regulator during all phases of the software life-cycle. The present publication was developed taking into account the large amount of available documentation, the rapid development of software systems and the need for updated guidance on h ow to do it . It provides information and guidance for defining and implementing quality assurance programmes covering the entire life-cycle of software important to safety. Expected users are managers, performers and assessors from nuclear utilities, regulatory bodies, suppliers and technical support organizations involved with the development and use of software applied in nuclear power plants

  10. Drug safety: Pregnancy rating classifications and controversies.

    Science.gov (United States)

    Wilmer, Erin; Chai, Sandy; Kroumpouzos, George

    2016-01-01

    This contribution consolidates data on international pregnancy rating classifications, including the former US Food and Drug Administration (FDA), Swedish, and Australian classification systems, as well as the evidence-based medicine system, and discusses discrepancies among them. It reviews the new Pregnancy and Lactation Labeling Rule (PLLR) that replaced the former FDA labeling system with narrative-based labeling requirements. PLLR emphasizes on human data and highlights pregnancy exposure registry information. In this context, the review discusses important data on the safety of most medications used in the management of skin disease in pregnancy. There are also discussions of controversies relevant to the safety of certain dermatologic medications during gestation. Copyright © 2016 Elsevier Inc. All rights reserved.

  11. Review of actinide nitride properties with focus on safety aspects

    Energy Technology Data Exchange (ETDEWEB)

    Albiol, Thierry [CEA Cadarache, St Paul Lez Durance Cedex (France); Arai, Yasuo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-12-01

    This report provides a review of the potential advantages of using actinide nitrides as fuels and/or targets for nuclear waste transmutation. Then a summary of available properties of actinide nitrides is given. Results from irradiation experiments are reviewed and safety relevant aspects of nitride fuels are discussed, including design basis accidents (transients) and severe (core disruptive) accidents. Anyway, as rather few safety studies are currently available and as many basic physical data are still missing for some actinide nitrides, complementary studies are proposed. (author)

  12. The Interface Between Safety and Security at Nuclear Power Plants. INSAG-24. A report by the International Nuclear Safety Group (Russian Edition)

    International Nuclear Information System (INIS)

    2014-01-01

    This publication seeks to provide a better understanding of the interface between safety and security at nuclear power plants and to discuss the means to achieve both objectives in an optimal fashion. It provides information in a background chapter on the existing relevant documentation, discusses the expectations for administrative arrangements at different levels, surveys certain common principles, and suggests general solutions that can help ensure an integrated approach. Conclusions are drawn and high level recommendations are proposed with the goal of maximizing the protection of the public, property, society and the environment through an improved and strengthened interface between safety and security

  13. Biologics in pediatric psoriasis - efficacy and safety.

    Science.gov (United States)

    Dogra, Sunil; Mahajan, Rahul

    2018-01-01

    Childhood psoriasis is a special situation that is a management challenge for the treating dermatologist. As is the situation with traditional systemic agents, which are commonly used in managing severe psoriasis in children, the biologics are being increasingly used in the recalcitrant disease despite limited data on long term safety. Areas covered: We performed an extensive literature search to collect evidence-based data on the use of biologics in pediatric psoriasis. The relevant literature published from 2000 to September 2017 was obtained from PubMed, using the MeSH words 'biologics', 'biologic response modifiers' and 'treatment of pediatric/childhood psoriasis'. All clinical trials, randomized double-blind or single-blind controlled trials, open-label studies, retrospective studies, reviews, case reports and letters concerning the use of biologics in pediatric psoriasis were screened. Articles covering the use of biologics in pediatric psoriasis were screened and reference lists in the selected articles were scrutinized to identify other relevant articles that had not been found in the initial search. Articles without relevant information about biologics in general (e.g. its mechanism of action, pharmacokinetics and adverse effects) and its use in psoriasis in particular were excluded. We screened 427 articles and finally selected 41 relevant articles. Expert opinion: The available literature on the use of biologics such as anti-tumor necrosis factor (TNF)-α agents, and anti-IL-12/23 agents like ustekinumab suggests that these are effective and safe in managing severe pediatric psoriasis although there is an urgent need to generate more safety data. Dermatologists must be careful about the potential adverse effects of the biologics before administering them to children with psoriasis. It is likely that with rapidly evolving scenario of biologics in psoriasis, these will prove to be very useful molecules particularly in managing severe and recalcitrant

  14. Safety assessment guidance in the International Atomic Energy Agency RADWASS Program

    Energy Technology Data Exchange (ETDEWEB)

    Vovk, I.F.; Seitz, R.R.

    1995-12-31

    The IAEA RADWASS programme is aimed at establishing a coherent and comprehensive set of principles and standards for the safe management of waste and formulating the guidelines necessary for their application. A large portion of this programme has been devoted to safety assessments for various waste management activities. Five Safety Guides are planned to be developed to provide general guidance to enable operators and regulators to develop necessary framework for safety assessment process in accordance with international recommendations. They cover predisposal, near surface disposal, geological disposal, uranium/thorium mining and milling waste, and decommissioning and environmental restoration. The Guide on safety assessment for near surface disposal is at the most advanced stage of preparation. This draft Safety Guide contains guidance on description of the disposal system, development of a conceptual model, identification and description of relevant scenarios and pathways, consequence analysis, presentation of results and confidence building. The set of RADWASS publications is currently undergoing in-depth review to ensure a harmonized approach throughout the Safety Series.

  15. Public perception of drinking water safety in South Africa 2002–2009: a repeated cross-sectional study

    Science.gov (United States)

    2012-01-01

    Background In low and middle income countries, public perceptions of drinking water safety are relevant to promotion of household water treatment and to household choices over drinking water sources. However, most studies of this topic have been cross-sectional and not considered temporal variation in drinking water safety perceptions. The objective of this study is to explore trends in perceived drinking water safety in South Africa and its association with disease outbreaks, water supply and household characteristics. Methods This repeated cross-sectional study draws on General Household Surveys from 2002–2009, a series of annual nationally representative surveys of South African households, which include a question about perceived drinking water safety. Trends in responses to this question were examined from 2002–2009 in relation to reported cholera cases. The relationship between perceived drinking water safety and organoleptic qualities of drinking water, supply characteristics, and socio-economic and demographic household characteristics was explored in 2002 and 2008 using hierarchical stepwise logistic regression. Results The results suggest that perceived drinking water safety has remained relatively stable over time in South Africa, once the expansion of improved supplies is controlled for. A large cholera outbreak in 2000–02 had no apparent effect on public perception of drinking water safety in 2002. Perceived drinking water safety is primarily related to water taste, odour, and clarity rather than socio-economic or demographic characteristics. Conclusion This suggests that household perceptions of drinking water safety in South Africa follow similar patterns to those observed in studies in developed countries. The stability over time in public perception of drinking water safety is particularly surprising, given the large cholera outbreak that took place at the start of this period. PMID:22834485

  16. Public perception of drinking water safety in South Africa 2002–2009: a repeated cross-sectional study

    Directory of Open Access Journals (Sweden)

    Wright Jim A

    2012-07-01

    Full Text Available Abstract Background In low and middle income countries, public perceptions of drinking water safety are relevant to promotion of household water treatment and to household choices over drinking water sources. However, most studies of this topic have been cross-sectional and not considered temporal variation in drinking water safety perceptions. The objective of this study is to explore trends in perceived drinking water safety in South Africa and its association with disease outbreaks, water supply and household characteristics. Methods This repeated cross-sectional study draws on General Household Surveys from 2002–2009, a series of annual nationally representative surveys of South African households, which include a question about perceived drinking water safety. Trends in responses to this question were examined from 2002–2009 in relation to reported cholera cases. The relationship between perceived drinking water safety and organoleptic qualities of drinking water, supply characteristics, and socio-economic and demographic household characteristics was explored in 2002 and 2008 using hierarchical stepwise logistic regression. Results The results suggest that perceived drinking water safety has remained relatively stable over time in South Africa, once the expansion of improved supplies is controlled for. A large cholera outbreak in 2000–02 had no apparent effect on public perception of drinking water safety in 2002. Perceived drinking water safety is primarily related to water taste, odour, and clarity rather than socio-economic or demographic characteristics. Conclusion This suggests that household perceptions of drinking water safety in South Africa follow similar patterns to those observed in studies in developed countries. The stability over time in public perception of drinking water safety is particularly surprising, given the large cholera outbreak that took place at the start of this period.

  17. Drug safety: withdrawn medications are only part of the picture.

    Science.gov (United States)

    Rawson, Nigel S B

    2016-02-13

    In a research article published in BMC Medicine, Onakpoya and colleagues provide a historical review of withdrawals of medications for safety reasons. However, withdrawn medications are only one part of the picture about how regulatory agencies manage drug risks. Moreover, medications introduced before the increased pre-marketing regulations and post-marketing monitoring systems instituted after the thalidomide tragedy have little relevance when considering the present drug safety picture because the circumstances under which they were introduced were completely different. To more fully understand drug safety management and regulatory agency actions, withdrawals should be evaluated within the setting and timeframe in which the medications are approved, which requires information about approvals and safety warnings. Studies are needed that provide a more comprehensive current picture of the identification and evaluation of drug safety risks as well as how regulatory agencies deal with them. Please see related research article: http://bmcmedicine.biomedcentral.com/articles/10.1186/s12916-016-0553-2.

  18. Nuclear reactors safety issues

    International Nuclear Information System (INIS)

    Barre, Francois; Seiler, Nathalie

    2008-01-01

    fuels as well as the applied methodologies. The IRSN proceeds in a relevant and independent assessment of the submitted safety reports. To achieve this goal and maintain over time an independent and relevant assessment capability, the IRSN relies on the excellence of its experts and on state of art techniques and knowledge. The IRSN contributes by its work in key area to cutting edge research and development in order to drive nuclear industry towards making the best use of scientific and technological progress for improving safety, environmental protection and health. To maintain at all times the state of the art knowledge and the operational expertise necessary to deal efficiently with major nuclear accident consequences, the IRSN carries out, on the one hand, its own research and development programs to gain accurate knowledge on still unknown phenomena for safety analysis. On the other hand, the IRSN works out its own scientific calculation methodologies involving industrial calculation chain. Concerning more particularly the 'two-phase flows' thematic, The ISRN must correctly simulate the primary fluid behavior in the reactor in normal operation as well as in accidental situations, to estimate if, in such situations, the core reactor state is fully safe and any safety risk is undergone The research and development programs launched at the ISRN on two-phase flows gather work on advanced thermohydraulic configurations encounter in various reactor states (normal operation or accidental situations), in particular: (i)The estimation of the margin to the critical heat flux in normal operation (DNBR), (ii) The pressurized thermal shock, which is due to mechanical important constraints in the reactor vessel resulting from the injection of a cold fluid in case of emergency cooling (PTS), (iii) The reactivity insertion accident (RIA), (iv) The loss of coolant accident (LOCA), (vi) The accidents in spent-fuel pools and (vii) The severe accident, which could lead to core

  19. Safety improvement programme of WWER 440/230 units in Jaslovske Bohunice

    International Nuclear Information System (INIS)

    Tomek, J.

    2000-01-01

    A brief overview is given of the power sources in Slovakia which include 6 operational reactor units (4 at Jaslovske Bohunice and 2 at Mochovce) and 2 units under construction (at Mochovce). The efforts undertaken in the past 10 years and aimed at upgrading the nuclear safety of the two older (V-230 Soviet type) units at Bohunice are highlighted. The relevant regulatory decisions are dealt with and the measures already carried out are listed. Also characterized are several IAEA international safety assessment missions and safety-aimed meetings which took place in 1998 and 1999 and are of concern to the older Bohunice units. (A.K.)

  20. Containment-emergency-sump performance. Technical findings related to Unresolved Safety Issue A-43

    International Nuclear Information System (INIS)

    1983-04-01

    This report summarizes key technical findings related to the Unresolved Safety Issue A-43, Containment Emergency Sump Performance, and provides recommendations for resolution of attendant safety issues. The key safety questions relate to: (a) effects of insulation debris on sump performance; (b) sump hydraulic performance as determined by design features, submergence, and plant induced effects, and (c) recirculation pump performance wherein air and/or particulate ingestion can occur. The technical findings presented in this report provide information relevant to the design and performance evaluation of the containment emergency sump

  1. Potential safety features and safety analysis aspects for high performance light water reactor (HPLWR)

    International Nuclear Information System (INIS)

    Aksan, N.; Schulenberg, T.; Squarer, D.

    2003-01-01

    Research Activities are ongoing worldwide to develop advanced nuclear power plants with high thermal efficiency for the purpose to improve their economical competitiveness. Within the 5th Framework Programme of the European Commission, a project has been launched with the main objective to assess the technical and economical feasibility of a high efficiency LWR operating at super critical pressure conditions. Several European research institutions, industrial partners and the University of Tokyo participated and worked in this common research project. Within the aims of the development of the HPLWR is to use both passive and active safety systems for performing safety related functions in the event of transients or accidents. Consequently substantial effort has been invested in order to define the safety features of the plant in a European environment, as well as to incorporate passive safety features into the design. Throughout this process, the European Utility Requirements (EUR) and requirements known from Generation IV initiative were considered as a guideline in general terms in order to include further advanced ideas. The HPLWR general features were compared to both requirements, indicating a potential to meet these. Since, the supercritical HPLWR represents a challenge for best-estimate safety codes like RELAP5, CATHARE and TRAB due to the fact that these codes were developed for two-phase or single-phase coolant at pressures far below critical point, work on the preliminary assessment of the appropriateness of these codes have been performed for selected relevant phenomena, and application of the codes to the selected transients on the basis of defined 'reference design'. An overview on their successful upgrade to supercritical pressures and application to some plant safety analysis are provided in the paper. Further elaborations in relation to future needs are also discussed. (author)

  2. Risk and safety perception on urban and rural roads: Effects of environmental features, driver age and risk sensitivity.

    Science.gov (United States)

    Cox, Jolene A; Beanland, Vanessa; Filtness, Ashleigh J

    2017-10-03

    The ability to detect changing visual information is a vital component of safe driving. In addition to detecting changing visual information, drivers must also interpret its relevance to safety. Environmental changes considered to have high safety relevance will likely demand greater attention and more timely responses than those considered to have lower safety relevance. The aim of this study was to explore factors that are likely to influence perceptions of risk and safety regarding changing visual information in the driving environment. Factors explored were the environment in which the change occurs (i.e., urban vs. rural), the type of object that changes, and the driver's age, experience, and risk sensitivity. Sixty-three licensed drivers aged 18-70 years completed a hazard rating task, which required them to rate the perceived hazardousness of changing specific elements within urban and rural driving environments. Three attributes of potential hazards were systematically manipulated: the environment (urban, rural); the type of object changed (road sign, car, motorcycle, pedestrian, traffic light, animal, tree); and its inherent safety risk (low risk, high risk). Inherent safety risk was manipulated by either varying the object's placement, on/near or away from the road, or altering an infrastructure element that would require a change to driver behavior. Participants also completed two driving-related risk perception tasks, rating their relative crash risk and perceived risk of aberrant driving behaviors. Driver age was not significantly associated with hazard ratings, but individual differences in perceived risk of aberrant driving behaviors predicted hazard ratings, suggesting that general driving-related risk sensitivity plays a strong role in safety perception. In both urban and rural scenes, there were significant associations between hazard ratings and inherent safety risk, with low-risk changes perceived as consistently less hazardous than high

  3. Introduction of Autonomous Vehicles: Roundabouts Design and Safety Performance Evaluation

    Directory of Open Access Journals (Sweden)

    Aleksandra Deluka Tibljaš

    2018-04-01

    Full Text Available Driving experiences provided by the introduction of new vehicle technologies are directly impacting the criteria for road network design. New criteria should be taken into consideration by designers, researchers and car owners in order to assure traffic safety in changed conditions that will appear with, for example, introduction of Autonomous Vehicles (AVs in everyday traffic. In this paper, roundabout safety level is analysed on the originally developed microsimulation model in circumstances where different numbers of AVs vehicles are mixed with Conventional Vehicles (CVs. Field data about speed and traffic volumes from existing roundabouts in Croatia were used for development of the model. The simulations done with the Surrogate Safety Assessment Model (SSAM give some relevant highlights on how the introduction of AVs could change both operational and safety parameters at roundabouts. To further explore the effects on safety of roundabouts with the introduction of different shares of AVs, hypothetical safety treatments could be tested to explore whether their effects may change, leading to the estimation of a new set of Crash Modification Factors.

  4. Rule-based Dynamic Safety Monitoring for Mobile Robots

    DEFF Research Database (Denmark)

    Adam, Marian Sorin; Larsen, Morten; Jensen, Kjeld

    2016-01-01

    Safety is a key challenge in robotics, in particular for mobile robots operating in an open and unpredictable environment. Safety certification is desired for commercial robots, but no existing approaches for addressing the safety challenge provide a clearly specified and isolated safety layer......, defined in an easily understandable way for facilitating safety certification. In this paper, we propose that functional-safety-critical concerns regarding the robot software be explicitly declared separately from the main program, in terms of externally observable properties of the software. Concretely...

  5. Safety assessment of the methanol extract of the stem bark of Amphimas pterocarpoides Harms: Acute and subchronic oral toxicity studies in Wistar rats

    Directory of Open Access Journals (Sweden)

    Job Tchoumtchoua

    2014-01-01

    Full Text Available Amphimas pterocarpoides Harms (Leguminosae is widely used traditionally in Central and West Africa for the treatment of various ailments. However, no data regarding its safety have been published until now. Thus, the present study aimed to investigate the potential toxicity of the methanol extract of the stem bark of Amphimas pterocarpoides (AP in Wistar rats following the OECD guidelines. In acute oral toxicity, female rats received a single dose of 2000 mg/kg of AP and were observed for 14 days. In subchronic toxicity, doses of 150, 300, 600 mg/kg/day of AP were given per os to rats (males and females for 28 days. No death and abnormal behaviors were observed in acute toxicity and the LD50 was estimated higher than 5000 mg/kg. In the subchronic study, AP induced no significant variation in body weight and relative weight of organs, whereas a delayed decrease of white blood cell count and granulocytes was observed. Inconsistent increase of the total cholesterol/high density lipoprotein was observed at 600 mg/kg in males. Such variation (not dose dependent and without biological relevance indicate a wide margin of safety for the traditional use of AP.

  6. Food safety--who is responsible?

    Science.gov (United States)

    Rollin, Bernard E

    2006-01-01

    Though scientists believe that issues of risk can be handled without appeal to values in general or ethics in particular, this is demonstrably false. The very notion of risk is enmeshed in a complex of social ethics. This is clearly true with regard to food safety. With this in mind, it is plausible to affirm that responsibility for food safety at a given point in the chain from producer to consumer rests with the person or entity under whose control the management of that risk most plausibly lies. This principle is illustrated with various examples and with clear cases of industry shouldering and avoiding responsibility. An additional ethical concern relevant to food safety arises from genetically modified foods. Given that the situation here is uncertain and risk unknown, it is hard to see who is responsible for managing such risks. It is arguable that this situation militates in favor of labeling, since consumers are in effect research subjects. The reasonable moral approach to risk we have outlined is jeopardized by the societal tendency towards "victimology" and abrogation of personal responsibility. In such a world, it is incumbent on industry to educate the public with regard to consumer minimization of food safety risks, the impossibility of zero-risk situations, and the economic costs to freedom of protectionism.

  7. Developing an OMERACT Core Outcome Set for Assessing Safety Components in Rheumatology Trials

    DEFF Research Database (Denmark)

    Klokker, Louise; Tugwell, Peter; Furst, Daniel E

    2016-01-01

    in such COS. The Outcome Measures in Rheumatology (OMERACT) Filter 2.0 emphasizes the importance of measuring harms. The Safety Working Group was reestablished at the OMERACT 2016 with the objective to develop a COS for assessing safety components in trials across rheumatologic conditions. METHODS: The safety......OBJECTIVE: Failure to report harmful outcomes in clinical research can introduce bias favoring a potentially harmful intervention. While core outcome sets (COS) are available for benefits in randomized controlled trials in many rheumatic conditions, less attention has been paid to safety...... that patients consider relevant so that they will be able to make informed decisions. CONCLUSION: The OMERACT Safety Working Group will advance the work previously done within OMERACT using a new patient-driven approach....

  8. Understanding safety and production risks in rail engineering planning and protection.

    Science.gov (United States)

    Wilson, John R; Ryan, Brendan; Schock, Alex; Ferreira, Pedro; Smith, Stuart; Pitsopoulos, Julia

    2009-07-01

    Much of the published human factors work on risk is to do with safety and within this is concerned with prediction and analysis of human error and with human reliability assessment. Less has been published on human factors contributions to understanding and managing project, business, engineering and other forms of risk and still less jointly assessing risk to do with broad issues of 'safety' and broad issues of 'production' or 'performance'. This paper contains a general commentary on human factors and assessment of risk of various kinds, in the context of the aims of ergonomics and concerns about being too risk averse. The paper then describes a specific project, in rail engineering, where the notion of a human factors case has been employed to analyse engineering functions and related human factors issues. A human factors issues register for potential system disturbances has been developed, prior to a human factors risk assessment, which jointly covers safety and production (engineering delivery) concerns. The paper concludes with a commentary on the potential relevance of a resilience engineering perspective to understanding rail engineering systems risk. Design, planning and management of complex systems will increasingly have to address the issue of making trade-offs between safety and production, and ergonomics should be central to this. The paper addresses the relevant issues and does so in an under-published domain - rail systems engineering work.

  9. Fuel Fracture (Crumbling) Safety Impact (OCRWM)

    International Nuclear Information System (INIS)

    DUNCAN, D.R.

    1999-01-01

    The safety impact of experimentally observed N Reactor fuel sample fracture and fragmentation is evaluated using an average reaction rate enhancement derived from data from thermo-gravimetric analysis (TGA) experiments on fuel samples. The enhanced reaction rates attributed to fragmentation were within the existing safety basis

  10. Impacts of a lengthening open water season on Alaskan coastal communities: deriving locally relevant indices from large-scale datasets and community observations

    Science.gov (United States)

    Rolph, Rebecca J.; Mahoney, Andrew R.; Walsh, John; Loring, Philip A.

    2018-05-01

    Using thresholds of physical climate variables developed from community observations, together with two large-scale datasets, we have produced local indices directly relevant to the impacts of a reduced sea ice cover on Alaska coastal communities. The indices include the number of false freeze-ups defined by transient exceedances of ice concentration prior to a corresponding exceedance that persists, false break-ups, timing of freeze-up and break-up, length of the open water duration, number of days when the winds preclude hunting via boat (wind speed threshold exceedances), the number of wind events conducive to geomorphological work or damage to infrastructure from ocean waves, and the number of these wind events with on- and along-shore components promoting water setup along the coastline. We demonstrate how community observations can inform use of large-scale datasets to derive these locally relevant indices. The two primary large-scale datasets are the Historical Sea Ice Atlas for Alaska and the atmospheric output from a regional climate model used to downscale the ERA-Interim atmospheric reanalysis. We illustrate the variability and trends of these indices by application to the rural Alaska communities of Kotzebue, Shishmaref, and Utqiaġvik (previously Barrow), although the same procedure and metrics can be applied to other coastal communities. Over the 1979-2014 time period, there has been a marked increase in the number of combined false freeze-ups and false break-ups as well as the number of days too windy for hunting via boat for all three communities, especially Utqiaġvik. At Utqiaġvik, there has been an approximate tripling of the number of wind events conducive to coastline erosion from 1979 to 2014. We have also found a delay in freeze-up and earlier break-up, leading to a lengthened open water period for all of the communities examined.

  11. Impacts of a lengthening open water season on Alaskan coastal communities: deriving locally relevant indices from large-scale datasets and community observations

    Directory of Open Access Journals (Sweden)

    R. J. Rolph

    2018-05-01

    Full Text Available Using thresholds of physical climate variables developed from community observations, together with two large-scale datasets, we have produced local indices directly relevant to the impacts of a reduced sea ice cover on Alaska coastal communities. The indices include the number of false freeze-ups defined by transient exceedances of ice concentration prior to a corresponding exceedance that persists, false break-ups, timing of freeze-up and break-up, length of the open water duration, number of days when the winds preclude hunting via boat (wind speed threshold exceedances, the number of wind events conducive to geomorphological work or damage to infrastructure from ocean waves, and the number of these wind events with on- and along-shore components promoting water setup along the coastline. We demonstrate how community observations can inform use of large-scale datasets to derive these locally relevant indices. The two primary large-scale datasets are the Historical Sea Ice Atlas for Alaska and the atmospheric output from a regional climate model used to downscale the ERA-Interim atmospheric reanalysis. We illustrate the variability and trends of these indices by application to the rural Alaska communities of Kotzebue, Shishmaref, and Utqiaġvik (previously Barrow, although the same procedure and metrics can be applied to other coastal communities. Over the 1979–2014 time period, there has been a marked increase in the number of combined false freeze-ups and false break-ups as well as the number of days too windy for hunting via boat for all three communities, especially Utqiaġvik. At Utqiaġvik, there has been an approximate tripling of the number of wind events conducive to coastline erosion from 1979 to 2014. We have also found a delay in freeze-up and earlier break-up, leading to a lengthened open water period for all of the communities examined.

  12. Data and methods for studying commercial motor vehicle driver fatigue, highway safety and long-term driver health.

    Science.gov (United States)

    Stern, Hal S; Blower, Daniel; Cohen, Michael L; Czeisler, Charles A; Dinges, David F; Greenhouse, Joel B; Guo, Feng; Hanowski, Richard J; Hartenbaum, Natalie P; Krueger, Gerald P; Mallis, Melissa M; Pain, Richard F; Rizzo, Matthew; Sinha, Esha; Small, Dylan S; Stuart, Elizabeth A; Wegman, David H

    2018-03-09

    This article summarizes the recommendations on data and methodology issues for studying commercial motor vehicle driver fatigue of a National Academies of Sciences, Engineering, and Medicine study. A framework is provided that identifies the various factors affecting driver fatigue and relating driver fatigue to crash risk and long-term driver health. The relevant factors include characteristics of the driver, vehicle, carrier and environment. Limitations of existing data are considered and potential sources of additional data described. Statistical methods that can be used to improve understanding of the relevant relationships from observational data are also described. The recommendations for enhanced data collection and the use of modern statistical methods for causal inference have the potential to enhance our understanding of the relationship of fatigue to highway safety and to long-term driver health. Copyright © 2018 The Authors. Published by Elsevier Ltd.. All rights reserved.

  13. Team of experts concludes review of safety issues at Temelin

    International Nuclear Information System (INIS)

    2001-01-01

    Full text: At the request of the Czech Government, the International Atomic Energy Agency (IAEA) assembled a team of national experts from Bulgaria, France, Germany, Spain, and the United Kingdom, with an observer from Austria, to review safety issues at the Temelin power plant that were identified in 1996 as relevant to reactors of the generic Temelin design (WWER-1000/320 type). Following a detailed on-site review from 18 to 23 November 2001, the experts concluded that most identified issues had been addressed and resolved. Work is continuing on the few remaining issues. These issues, however, are not judged by them to be significant and would not from the experts' standpoint preclude the safe operation of the Temelin nuclear power plant. The final report of the team of experts will be available to the Czech Government in one month's time. (author)

  14. Review of Policy Documents for Nuclear Safety and Regulation

    International Nuclear Information System (INIS)

    Kim, Woong Sik; Choi, Kwang Sik; Choi, Young Sung; Kim, Hho Jung; Kim, Ho Ki

    2006-01-01

    The goal of regulation is to protect public health and safety as well as environment from radiological hazards that may occur as a result of the use of atomic energy. In September 1994, the Korean government issued the Nuclear Safety Policy Statement (NSPS) to establish policy goals of maintaining and achieving high-level of nuclear safety and also help the public understand the national policy and a strong will of the government toward nuclear safety. It declares the importance of establishing safety culture in nuclear community and also specifies five nuclear regulatory principles (Independence, Openness, Clarity, Efficiency and Reliability) and provides the eleven regulatory policy directions. In 2001, the Nuclear Safety Charter was declared to make the highest goal of safety in driving nuclear business clearer; to encourage atomic energy- related institutions and workers to keep in mind the mission and responsibility for assuring safety; to guarantee public confidence in related organizations. The Ministry of Science and Technology (MOST) also issues Yearly Regulatory Policy Directions at the beginning of every year. Recently, the third Atomic Energy Promotion Plan (2007-2011) has been established. It becomes necessary for the relevant organizations to prepare the detailed plans on such areas as nuclear development, safety management, regulation, etc. This paper introduces a multi-level structure of nuclear safety and regulation policy documents in Korea and presents some improvements necessary for better application of the policies

  15. Review of Policy Documents for Nuclear Safety and Regulation

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Woong Sik; Choi, Kwang Sik; Choi, Young Sung; Kim, Hho Jung; Kim, Ho Ki [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)

    2006-07-01

    The goal of regulation is to protect public health and safety as well as environment from radiological hazards that may occur as a result of the use of atomic energy. In September 1994, the Korean government issued the Nuclear Safety Policy Statement (NSPS) to establish policy goals of maintaining and achieving high-level of nuclear safety and also help the public understand the national policy and a strong will of the government toward nuclear safety. It declares the importance of establishing safety culture in nuclear community and also specifies five nuclear regulatory principles (Independence, Openness, Clarity, Efficiency and Reliability) and provides the eleven regulatory policy directions. In 2001, the Nuclear Safety Charter was declared to make the highest goal of safety in driving nuclear business clearer; to encourage atomic energy- related institutions and workers to keep in mind the mission and responsibility for assuring safety; to guarantee public confidence in related organizations. The Ministry of Science and Technology (MOST) also issues Yearly Regulatory Policy Directions at the beginning of every year. Recently, the third Atomic Energy Promotion Plan (2007-2011) has been established. It becomes necessary for the relevant organizations to prepare the detailed plans on such areas as nuclear development, safety management, regulation, etc. This paper introduces a multi-level structure of nuclear safety and regulation policy documents in Korea and presents some improvements necessary for better application of the policies.

  16. Quality and safety control in the production of recreational-purpose cottage cheese

    OpenAIRE

    Мостова, Людмила Миколаївна; Клусович, Тетяна Валеріївна

    2015-01-01

    The paper deals with the relevant problem of implementing safety control systems according to HACCP principles for Ukrainian catering establishments in the integration of trade space. Taking into account high competition and consumer audience gaining priority, the work emphasizes the need to develop and implement safety control system according to HACCP principles as a precondition for leadership of catering establishments  in the national market, and get significant competitive advantages in...

  17. Do women on management board increase fair value relevance?

    OpenAIRE

    Velte, Patrick

    2017-01-01

    The purpose of this paper is the link between women on management board and the value relevance of fair value accounting according to IFRS 13. The empirical quantitative study covers a sample of German companies listed at the Prime Standard of the Frankfurt Stock Exchange for the business years 2013-2015 (411 firm-year observations). Value relevance is measured by the modified Ohlson (1995) model and we separate fair value accounting in level 1, level 2 and level 3 fair values. Multiple regre...

  18. Buffer and backfill process report for the safety assessment SR-Can

    Energy Technology Data Exchange (ETDEWEB)

    Sellin, Patrik (comp.)

    2006-09-15

    This document compiles information on processes in the buffer and deposition tunnel backfill relevant for long-term safety of a KBS-repository. It supports the safety assessment SR-Can, which is a preparatory step for a safety assessment that will support the licence application for a final repository in Sweden. The purpose of the process reports is to document the scientific knowledge of the processes to a level required for an adequate treatment of the processes in the safety assessment. The documentation is not exhaustive from a scientific point of view, since such a treatment is neither necessary for the purposes of the safety assessment nor possible within the scope of an assessment. However, it must be sufficiently detailed to motivate, by arguments founded on scientific understanding, the treatment of each process in the safety assessment. The purpose is further to determine how to handle each process in the safety assessment at an appropriate degree of detail, and to demonstrate how uncertainties are taken care of, given the suggested handling.

  19. Buffer and backfill process report for the safety assessment SR-Can

    International Nuclear Information System (INIS)

    Sellin, Patrik

    2006-09-01

    This document compiles information on processes in the buffer and deposition tunnel backfill relevant for long-term safety of a KBS-repository. It supports the safety assessment SR-Can, which is a preparatory step for a safety assessment that will support the licence application for a final repository in Sweden. The purpose of the process reports is to document the scientific knowledge of the processes to a level required for an adequate treatment of the processes in the safety assessment. The documentation is not exhaustive from a scientific point of view, since such a treatment is neither necessary for the purposes of the safety assessment nor possible within the scope of an assessment. However, it must be sufficiently detailed to motivate, by arguments founded on scientific understanding, the treatment of each process in the safety assessment. The purpose is further to determine how to handle each process in the safety assessment at an appropriate degree of detail, and to demonstrate how uncertainties are taken care of, given the suggested handling

  20. Safety culture: a comparative study of space, nuclear and oil-gas sectors

    International Nuclear Information System (INIS)

    Morais, David; Assis, Altair Souza de

    2008-01-01

    Full text:We access in this paper the safety culture methodology adopted by three different industrial sectors: Nuclear, space/aeronautics and oil-gas, in Brazil. In this work, It is evaluated the planning, training, personal monitoring and the interaction between the technical personal, such as engineers and physicists, with human ones, such social workers and physiologists, key factor to understand the efficacy of the local safety culture pattern. The research is made through the analysis of the relevant manuals and interviewing the safety, human areas personal, and regulatory managers, concerned with/related to safety/working with safety culture at the specific industrial sector. It is compared the efficacies and the official regulatory vision on the issue, for the different sectors, in order to detect confluences and divergences and, so, to propose a model that better treat the safety culture as a global industrial value. (author)

  1. Effects of auditing patient safety in hospital care: design of a mixed-method evaluation

    Science.gov (United States)

    2013-01-01

    Background Auditing of patient safety aims at early detection of risks of adverse events and is intended to encourage the continuous improvement of patient safety. The auditing should be an independent, objective assurance and consulting system. Auditing helps an organisation accomplish its objectives by bringing a systematic, disciplined approach to evaluating and improving the effectiveness of risk management, control, and governance. Audits are broadly conducted in hospitals, but little is known about their effects on the behaviour of healthcare professionals and patient safety outcomes. This study was initiated to evaluate the effects of patient safety auditing in hospital care and to explore the processes and mechanisms underlying these effects. Methods and design Our study aims to evaluate an audit system to monitor and improve patient safety in a hospital setting. We are using a mixed-method evaluation with a before-and-after study design in eight departments of one university hospital in the period October 2011–July 2014. We measure several outcomes 3 months before the audit and 15 months after the audit. The primary outcomes are adverse events and complications. The secondary outcomes are experiences of patients, the standardised mortality ratio, prolonged hospital stay, patient safety culture, and team climate. We use medical record reviews, questionnaires, hospital administrative data, and observations to assess the outcomes. A process evaluation will be used to find out which components of internal auditing determine the effects. Discussion We report a study protocol of an effect and process evaluation to determine whether auditing improves patient safety in hospital care. Because auditing is a complex intervention targeted on several levels, we are using a combination of methods to collect qualitative and quantitative data about patient safety at the patient, professional, and department levels. This study is relevant for hospitals that want to

  2. Safety assessment and quality control of medical x-ray facilities in some hospitals in Ghana

    International Nuclear Information System (INIS)

    Darko, E.O.; Charles, D.F.

    1998-01-01

    Safety assessment and quality control measurements of diagnostic x-ray installations were carried out in five hospitals in Ghana. The study was focused on the siting, design and construction of the buildings housing the x-ray units, assessment of safety systems and devices and measurements of the technical performance, and film processing conditions. The location, inadequacies in the design/construction, unavailability of relevant safety systems and devices, violation of basic safety principles and poor performance of some of the x-ray facilities indicate the need to improve quality control programmes, safety culture and enforcement of regulatory standards in diagnostic x-ray examinations in Ghana. (author). 8 refs., 11 tabs., 8 figs

  3. Safety of Transcranial Direct Current Stimulation: Evidence Based Update 2016.

    Science.gov (United States)

    Bikson, Marom; Grossman, Pnina; Thomas, Chris; Zannou, Adantchede Louis; Jiang, Jimmy; Adnan, Tatheer; Mourdoukoutas, Antonios P; Kronberg, Greg; Truong, Dennis; Boggio, Paulo; Brunoni, André R; Charvet, Leigh; Fregni, Felipe; Fritsch, Brita; Gillick, Bernadette; Hamilton, Roy H; Hampstead, Benjamin M; Jankord, Ryan; Kirton, Adam; Knotkova, Helena; Liebetanz, David; Liu, Anli; Loo, Colleen; Nitsche, Michael A; Reis, Janine; Richardson, Jessica D; Rotenberg, Alexander; Turkeltaub, Peter E; Woods, Adam J

    2016-01-01

    This review updates and consolidates evidence on the safety of transcranial Direct Current Stimulation (tDCS). Safety is here operationally defined by, and limited to, the absence of evidence for a Serious Adverse Effect, the criteria for which are rigorously defined. This review adopts an evidence-based approach, based on an aggregation of experience from human trials, taking care not to confuse speculation on potential hazards or lack of data to refute such speculation with evidence for risk. Safety data from animal tests for tissue damage are reviewed with systematic consideration of translation to humans. Arbitrary safety considerations are avoided. Computational models are used to relate dose to brain exposure in humans and animals. We review relevant dose-response curves and dose metrics (e.g. current, duration, current density, charge, charge density) for meaningful safety standards. Special consideration is given to theoretically vulnerable populations including children and the elderly, subjects with mood disorders, epilepsy, stroke, implants, and home users. Evidence from relevant animal models indicates that brain injury by Direct Current Stimulation (DCS) occurs at predicted brain current densities (6.3-13 A/m(2)) that are over an order of magnitude above those produced by conventional tDCS. To date, the use of conventional tDCS protocols in human trials (≤40 min, ≤4 milliamperes, ≤7.2 Coulombs) has not produced any reports of a Serious Adverse Effect or irreversible injury across over 33,200 sessions and 1000 subjects with repeated sessions. This includes a wide variety of subjects, including persons from potentially vulnerable populations. Copyright © 2016 Elsevier Inc. All rights reserved.

  4. Evidence on Adrenaline Use in Resuscitation and Its Relevance to Newborn Infants: A Non-Systematic Review.

    Science.gov (United States)

    Pinto, Merlin; Solevåg, Anne Lee; OʼReilly, Megan; Aziz, Khalid; Cheung, Po-Yin; Schmölzer, Georg M

    2017-01-01

    Guidelines for newborn resuscitation state that if the heart rate does not increase despite adequate ventilation and chest compressions, adrenaline administration should be considered. However, controversy exists around the safety and effectiveness of adrenaline in newborn resuscitation. The aim of this review was to summarise a selection of the current knowledge about adrenaline during resuscitation and evaluate its relevance to newborn infants. A search in PubMed, Embase, and Google Scholar until September 1, 2015, using search terms including adrenaline/epinephrine, cardiopulmonary resuscitation, death, severe brain injury, necrotizing enterocolitis, bronchopulmonary dysplasia, and adrenaline versus vasopressin/placebo. Adult data indicate that adrenaline improves the return of spontaneous circulation (ROSC) but not survival to hospital discharge. Newborn animal studies reported that adrenaline might be needed to achieve ROSC. Intravenous administration (10-30 μg/kg) is recommended; however, if there is no intravenous access, a higher endotracheal dose (50-100 μg/kg) is needed. The safety and effectiveness of intraosseous adrenaline remain undetermined. Early and frequent dosing does not seem to be beneficial. In fact, negative hemodynamic effects have been observed, especially with doses ≥30 μg/kg intravenously. Little is known about adrenaline in birth asphyxia and in preterm infants, but observations indicate that hemodynamics and neurological outcomes may be impaired by adrenaline administration in these conditions. However, a causal relationship between adrenaline administration and outcomes cannot be established from the few available retrospective studies. Alternative vasoconstrictors have been investigated, but the evidence is scarce. More research is needed on the benefits and risks of adrenaline in asphyxia-induced bradycardia or cardiac arrest during perinatal transition. © 2016 S. Karger AG, Basel.

  5. Engineering and Safety Partnership Enhances Safety of the Space Shuttle Program (SSP)

    Science.gov (United States)

    Duarte, Alberto

    2007-01-01

    Project Management must use the risk assessment documents (RADs) as tools to support their decision making process. Therefore, these documents have to be initiated, developed, and evolved parallel to the life of the project. Technical preparation and safety compliance of these documents require a great deal of resources. Updating these documents after-the-fact not only requires substantial increase in resources - Project Cost -, but this task is also not useful and perhaps an unnecessary expense. Hazard Reports (HRs), Failure Modes and Effects Analysis (FMEAs), Critical Item Lists (CILs), Risk Management process are, among others, within this category. A positive action resulting from a strong partnership between interested parties is one way to get these documents and related processes and requirements, released and updated in useful time. The Space Shuttle Program (SSP) at the Marshall Space Flight Center has implemented a process which is having positive results and gaining acceptance within the Agency. A hybrid Panel, with equal interest and responsibilities for the two larger organizations, Safety and Engineering, is the focal point of this process. Called the Marshall Safety and Engineering Review Panel (MSERP), its charter (Space Shuttle Program Directive 110 F, April 15, 2005), and its Operating Control Plan emphasizes the technical and safety responsibilities over the program risk documents: HRs; FMEA/CILs; Engineering Changes; anomalies/problem resolutions and corrective action implementations, and trend analysis. The MSERP has undertaken its responsibilities with objectivity, assertiveness, dedication, has operated with focus, and has shown significant results and promising perspectives. The MSERP has been deeply involved in propulsion systems and integration, real time technical issues and other relevant reviews, since its conception. These activities have transformed the propulsion MSERP in a truly participative and value added panel, making a

  6. Challenges of communicating safety case results to different audiences

    International Nuclear Information System (INIS)

    Hocke, Peter; Roehlig, Klaus-Juergen

    2014-01-01

    Nowadays, nuclear politics and decision making are often oriented at procedures which are linked to precautionary concepts and which reflect forms of 'knowledge politics'. These precautionary concepts in most cases focus on robust societal decisions, which incorporate the principles of sustainability as a topic of public debate. The issue of high-level nuclear waste is under debate and confronted with public discourse, which integrates not only the knowledge of different stakeholders, but also accept certain forms of 'Nichtwissen' ('non-knowledge'). Interdisciplinary research has to observe these normative trends and also has to 'contextualise' these questions before interpreting its research results for giving answers with practical relevance, especially in communication with different social actors. Issues which are brought up in this field of nuclear waste management and their social context have to be analysed in two dimensions: i) the dimension of professionalism and expertise; ii) the dimension of managing controversial debates ('knowledge politics') and the preparation and implementing of robust decisions mostly by responsible governmental organisations. In this context on the one hand complex aspects of safety have to be communicated in their internal scientific logic and structure. On the other hand the different functional systems and collective actors of highly differentiated modern societies are engaged in controversial debates on advanced technologies like nuclear energy and technologies for waste disposal over long-lasting time periods. Most safety and construction issues for final disposal of high-level waste, but also of waste management in general, are debated within professional 'communities' of scientists and experts. But if their technological artefacts and their conceptual planning become issues of controversial and political debates in spheres which are outside the closed circle of high-level professionals and party politicians (who are in the

  7. Design of an Active Automotive Safety System

    Directory of Open Access Journals (Sweden)

    Y. Wang

    2013-07-01

    Full Text Available With the development of the national economy, the people's standard of living got corresponding improvement, cars has been one of the indispensable traffic tools in many families. An active safety system is proposed, which can real-time detect the vehicle's running status and judge the security status of the vehicle. The system, which takes single-chip microcomputer as the controlling core and combines with millimeter-wave and ultrasonic distance measurement technology, can detect the distance from vehicle to vehicle and judge the security status of the vehicle. The hardware composition of the system and the data acquiring circuit are proposed, the mathematic model for different situation is established, and the controlling algorithm is completed. This system can accurately measure speed and distance between vehicles; the active safety control system can meet the relevant data measurement and transmission requirement; and can meet the functional requirement of the active safety control system

  8. Towards an integrated approach in supporting microbiological food safety decisions

    DEFF Research Database (Denmark)

    Havelaar, A.H.; Braunig, J.; Christiansen, K.

    2007-01-01

    an integrated scientific approach combining veterinary and medical epidemiology, risk assessment for the farm-to-fork food chain as well as agricultural and health economy. Scientific advice is relevant in all stages of the policy cycle: to assess the magnitude of the food safety problem, to define...

  9. Safety assessment for facilities and activities. General safety requirements. Pt. 4

    International Nuclear Information System (INIS)

    2009-01-01

    Fundamental Safety Principles. Section 3 describes the graded approach to implementation of the requirements for safety assessment for different facilities and activities. Section 4 establishes the overall requirements for a safety assessment and specific requirements that relate to the assessment of features relevant to safety. Section 4 also establishes the requirements to address defence in depth and safety margins, to perform safety analysis, to document the safety assessment and to carry out an independent verification. Section 5 establishes the requirements for the management, use and maintenance of the safety assessment

  10. Safety Assessment for Facilities and Activities. General Safety Requirements. Pt. 4

    International Nuclear Information System (INIS)

    2009-01-01

    Fundamental Safety Principles. Section 3 describes the graded approach to implementation of the requirements for safety assessment for different facilities and activities. Section 4 establishes the overall requirements for a safety assessment and specific requirements that relate to the assessment of features relevant to safety. Section 4 also establishes the requirements to address defence in depth and safety margins, to perform safety analysis, to document the safety assessment and to carry out an independent verification. Section 5 establishes the requirements for the management, use and maintenance of the safety assessment

  11. Safety Assessment for Facilities and Activities. General Safety Requirements. Pt. 4

    International Nuclear Information System (INIS)

    2010-01-01

    Fundamental Safety Principles. Section 3 describes the graded approach to implementation of the requirements for safety assessment for different facilities and activities. Section 4 establishes the overall requirements for a safety assessment and specific requirements that relate to the assessment of features relevant to safety. Section 4 also establishes the requirements to address defence in depth and safety margins, to perform safety analysis, to document the safety assessment and to carry out an independent verification. Section 5 establishes the requirements for the management, use and maintenance of the safety assessment

  12. Safety Assessment for Facilities and Activities. General Safety Requirements. Pt. 4

    International Nuclear Information System (INIS)

    2009-01-01

    from the Fundamental Safety Principles. Section 3 describes the graded approach to implementation of the requirements for safety assessment for different facilities and activities. Section 4 establishes the overall requirements for a safety assessment and specific requirements that relate to the assessment of features relevant to safety. Section 4 also establishes the requirements to address defence in depth and safety margins, to perform safety analysis, to document the safety assessment and to carry out an independent verification. Section 5 establishes the requirements for the management, use and maintenance of the safety assessment

  13. Safety in decommissioning of research reactors

    International Nuclear Information System (INIS)

    1986-01-01

    This Guide covers the technical and administrative considerations relevant to the nuclear aspects of safety in the decommissioning of reactors, as they apply to the reactor and the reactor site. While the treatment, transport and disposal of radioactive wastes arising from decommissioning are important considerations, these aspects are not specifically covered in this Guide. Likewise, other possible issues in decommissioning (e.g. land use and other environmental issues, industrial safety, financial assurance) which are not directly related to radiological safety are also not considered. Generally, decommissioning will be undertaken after planned final shutdown of the reactor. In some cases a reactor may have to be decommissioned following an unplanned or unexpected event of a series or damaging nature occurring during operation. In these cases special procedures for decommissioning may need to be developed, peculiar to the particular circumstances. This Guide could be used as a basis for the development of these procedures although specific consideration of the circumstances which create the need for them is beyond its scope

  14. Job safety in magnetic particle inspection

    International Nuclear Information System (INIS)

    Gallardo, Gerald S.

    2007-01-01

    Safety in the workplace is utmost importance to both employees and employers. It is a shared responsibility to make safety a way of life. General precautions to be exercised when performing magnetic particle inspection include consideration of exposure to oils, paste, and electrical current. It is important that the following minimum safety requirement to be observed when performing magnetic particle inspection. Always consult the Material Safety Data Sheet (MSDS) for the specific product or products you will be using to insure all necessary safety precautions are taken for potential health effects, first aid, fire hazard, accidental release measures, exposure controls, personal protection, physical properties,stability, reactivity toxicological information, disposal and transportation. (author)

  15. Radiological safety aspects of the operation of neutron generators

    International Nuclear Information System (INIS)

    Boggs, R.F.

    1976-01-01

    The purpose of the manual is to provide some basic guidelines to persons with a minimum of training in radiological health or health physics, on some safety aspects of the operation of sealed-tube and Cockcroft-Walton type neutron generators. The manual does not state rules or regulations but presents a description of the most likely hazards. It is relevant to those relatively compact neutron generators which usually operate at less than 150-200 kV for the purpose of producing 14-MeV neutrons. The scope is limited to basic discussions of hazards and measurement techniques. Separate chapters are devoted to the characteristics and use of neutron generators; radiation hazards and safety considerations; radiation monitoring and interpretation of measurements; and requirements for an effective safety programme. Two appendices deal with non-radiation hazards and safety considerations, and with a neutron generator laboratory, respectively. An extensive list of bibliographic references is included

  16. Safety assessment of a lithium target

    International Nuclear Information System (INIS)

    Burgazzi, Luciano; Roberta, Ferri; Barbara, Giannone

    2006-01-01

    This paper addresses the safety assessment of the lithium target of the International Fusion Materials Irradiation Facility (IFMIF) through evaluating the most important risk factors related to system operation and verifying the fulfillment of the safety criteria. The hazard assessment is based on using a well-structured Failure Mode and Effect Analysis (FMEA) procedure by detailing on a component-by-component basis all the possible failure modes and identifying their effects on the plant. Additionally, a systems analysis, applying the fault tree technique, is performed in order to evaluate, from a probabilistic standpoint, all the relevant and possible failures of each component required for safe system operation and assessing the unavailability of the lithium target system. The last task includes the thermal-hydraulic transient analysis of the target lithium loop, including operational and accident transients. A lithium target loop model is developed, using the RELAP5/Mod3.2 thermal-hydraulic code, which has been modified to include specific features of IFMIF itself. The main conclusions are that target safety is fulfilled, the hazards associated with lithium operation are confined within the IFMIF security boundaries, the environmental impact is negligible, and the plant responds to the simulated transients by being able to reach steady conditions in a safety situation

  17. The work of the Operational Safety Review Team (OSART)

    International Nuclear Information System (INIS)

    Hide, K.W.

    1996-01-01

    The Operational Safety Review Team (OSART) programme was set up by the IAEA in 1982 to assist Member States to enhance the operational safety of nuclear power plants. Each team is staffed by senior experts in the relevant fields. The review team discusses with plant staff the existing operational programmes for plant which may be under construction, being commissioned or already operating. Following a detailed examination of a safety programme, the OSART team lists strengths and weaknesses and makes recommendations on how to overcome the latter. Since their conclusions are based on the best prevailing international practice, they may be more stringent than those based on national criteria. The results of the 77 missions conducted at 62 plants in 28 countries by the end of 1994 are summarised. (UK)

  18. [Learning from errors: applying aviation safety concepts to medicine].

    Science.gov (United States)

    Sommer, K-J

    2012-11-01

    Health care safety levels range below other complex industries. Civil aviation has throughout its history developed methods and concepts that have made the airplane into one of the safest means of mass transport. Key elements are accident investigations that focus on cause instead of blame, human-centered design of machinery and processes, continuous training of all personnel and a shared safety culture. These methods and concepts can basically be applied to medicine which has successfully been achieved in certain areas, however, a comprehensive implementation remains to be completed. This applies particularly to including the topic of safety into relevant curricula. Physicians are obliged by the oath"primum nil nocere" to act, but economic as well as political pressure will eventually confine professional freedom if initiative is not taken soon.

  19. Safety culture enhancement through the implementation of IAEA guidelines

    International Nuclear Information System (INIS)

    Mengolini, A.; Debarberis, L.

    2007-01-01

    This paper presents the methodology applied and the results achieved in adapting and implementing the IAEA guidelines on safety culture to a research reactor as a step towards supporting its Life Management Program. The background is presented together with the effort undertaken to develop awareness on safety culture and the enhancement programme hereafter developed. The present study shows how issues of safety culture, management awareness and commitment deserve attention and can be of fundamental relevance also for research reactors. The study presents how guidelines developed specifically for nuclear power installations (NPPs) can be adapted to meet the needs and peculiarities of other nuclear installations. Moreover, the difficulties met during the implementation of the guidelines are discussed and important information and lessons can be learnt for the nuclear industry in general

  20. Indicators to monitor NPP operational safety performance

    International Nuclear Information System (INIS)

    Gomez-Cobo, Ana

    2002-01-01

    Since December 1995 the IAEA activities on safety performance indicators focused on the elaboration of a framework for the establishment of an operational safety performance indicator programme. The development of this framework began with the consideration of the concept of NPP operational safety performance and the identification of operational safety attributes. For each operational safety attribute, overall indicators, envisioned as providing an overall evaluation of relevant aspects of safety performance, were established. Associated with each overall indicator is a level of strategic indicators intended to provide a bridge from overall to specific indicators. Finally each strategic indicator was supported by a set of specific indicators, which represent quantifiable measures of performance. The programme development was enhanced by pilot plant studies, conducted over a 15 month period from January 1998 to March 1999. The result of all this work is compiled in the IAEA-TECDOC-1141, to be published shortly. This paper presents a summary of this IAEA TECDOC. It describes the operational safety performance indicator framework proposed and discusses the results of and lessons learned from the pilot studies. Despite the efforts described, it is clear that additional research is still necessary in areas such as plant-specific adaptation of proposed frameworks in order to suit individual data collection systems and plant characteristics, indicator selection, indicator definition, goal setting, action thresholds, analysis of trends, indicator display systems, analysis of overall safety performance (i.e., aggregation or combination of indicators), safety culture indicators, qualitative indicators, and use of additional indicators to address issues such as industrial safety attitude and performance, staff welfare, and environmental compliance. This is the rationale for a new IAEA Coordinated Research Project on 'Development and application of indicators to monitor NPP

  1. Development of a Novel Nuclear Safety Culture Evaluation Method for an Operating Team Using Probabilistic Safety Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Han, Sangmin; Lee, Seung Min; Seong, Poong Hyun [KAIST, Daejeon (Korea, Republic of)

    2015-05-15

    IAEA defined safety culture as follows: 'Safety Culture is that assembly of characteristics and attitudes in organizations and individuals which establishes that, as an overriding priority, nuclear plant safety issues receive the attention warranted by their significance'. Also, celebrated behavioral scientist, Cooper, defined safety culture as,'safety culture is that observable degree of effort by which all organizational members direct their attention and actions toward improving safety on a daily basis' with his internal psychological, situational, and behavioral context model. With these various definitions and criteria of safety culture, several safety culture assessment methods have been developed to improve and manage safety culture. To develop a new quantitative safety culture evaluation method for an operating team, we unified and redefined safety culture assessment items. Then we modeled a new safety culture evaluation by adopting level 1 PSA concept. Finally, we suggested the criteria to obtain nominal success probabilities of assessment items by using 'operational definition'. To validate the suggested evaluation method, we analyzed the collected audio-visual recording data collected from a full scope main control room simulator of a NPP in Korea.

  2. Development of a Novel Nuclear Safety Culture Evaluation Method for an Operating Team Using Probabilistic Safety Analysis

    International Nuclear Information System (INIS)

    Han, Sangmin; Lee, Seung Min; Seong, Poong Hyun

    2015-01-01

    IAEA defined safety culture as follows: 'Safety Culture is that assembly of characteristics and attitudes in organizations and individuals which establishes that, as an overriding priority, nuclear plant safety issues receive the attention warranted by their significance'. Also, celebrated behavioral scientist, Cooper, defined safety culture as,'safety culture is that observable degree of effort by which all organizational members direct their attention and actions toward improving safety on a daily basis' with his internal psychological, situational, and behavioral context model. With these various definitions and criteria of safety culture, several safety culture assessment methods have been developed to improve and manage safety culture. To develop a new quantitative safety culture evaluation method for an operating team, we unified and redefined safety culture assessment items. Then we modeled a new safety culture evaluation by adopting level 1 PSA concept. Finally, we suggested the criteria to obtain nominal success probabilities of assessment items by using 'operational definition'. To validate the suggested evaluation method, we analyzed the collected audio-visual recording data collected from a full scope main control room simulator of a NPP in Korea

  3. Alpha power gates relevant information during working memory updating.

    Science.gov (United States)

    Manza, Peter; Hau, Chui Luen Vera; Leung, Hoi-Chung

    2014-04-23

    Human working memory (WM) is inherently limited, so we must filter out irrelevant information in our environment or our mind while retaining limited important relevant contents. Previous work suggests that neural oscillations in the alpha band (8-14 Hz) play an important role in inhibiting incoming distracting information during attention and selective encoding tasks. However, whether alpha power is involved in inhibiting no-longer-relevant content or in representing relevant WM content is still debated. To clarify this issue, we manipulated the amount of relevant/irrelevant information using a task requiring spatial WM updating while measuring neural oscillatory activity via EEG and localized current sources across the scalp using a surface Laplacian transform. An initial memory set of two, four, or six spatial locations was to be memorized over a delay until an updating cue was presented indicating that only one or three locations remained relevant for a subsequent recognition test. Alpha amplitude varied with memory maintenance and updating demands among a cluster of left frontocentral electrodes. Greater postcue alpha power was associated with the high relevant load conditions (six and four dots cued to reduce to three relevant) relative to the lower load conditions (four and two dots reduced to one). Across subjects, this difference in alpha power was correlated with condition differences in performance accuracy. In contrast, no significant effects of irrelevant load were observed. These findings demonstrate that, during WM updating, alpha power reflects maintenance of relevant memory contents rather than suppression of no-longer-relevant memory traces.

  4. Nurses' but not supervisors' safety practices are linked with job satisfaction.

    Science.gov (United States)

    Hurtado, David A; Kim, Seung-Sup; Subramanian, S V; Dennerlein, Jack T; Christiani, David C; Hashimoto, Dean M; Sorensen, Glorian

    2017-10-01

    To test the associations of safety practices as reported by nurses and their respective unit supervisors with job satisfaction. Psychosocial workplace factors are associated with job satisfaction; however, it is unknown whether nurses and supervisors accounts of safety practices are differentially linked to this outcome. Cross-sectional study design including nurses (n = 1052) nested in 94 units in two hospitals in Boston (MA, USA). Safety practices refer to the identification and control of occupational hazards at the unit. Safety practices were measured aggregating nurses' responses per unit, and supervisory levels. Individual's job satisfaction for each nurse was the response variable. Supervisors assessed safety practices more favourably than their unit nursing staff. Adjusted random intercept logistic regressions showed that the odds of higher job satisfaction were higher for nurses at units with better safety practices (OR: 1.67, 95% CI: 1.04, 2.68) compared with nurses at units that averaged lower safety practices. Supervisors' reports of safety practices were not correlated with the job satisfaction of their staff. Adequate safety practices might be a relevant managerial role that enhances job satisfaction among nurses. Nursing supervisors should calibrate their safety assessments with their nursing staff to improve nurses' job satisfaction. © 2017 John Wiley & Sons Ltd.

  5. Case study: an evaluation of the human relevance of the synthetic pyrethroid metofluthrin-induced liver tumors in rats based on mode of action.

    Science.gov (United States)

    Yamada, Tomoya; Uwagawa, Satoshi; Okuno, Yasuyoshi; Cohen, Samuel M; Kaneko, Hideo

    2009-03-01

    In recent years, mode of action (MOA) frameworks have been developed through the International Life Sciences Institute Risk Science Institute and the International Programme on Chemical Safety, including an evaluation of the human relevance of the animal MOA data. In the present paper, the MOA for rat liver tumors induced by Metofluthrin is first analyzed through this framework based on data from studies on Metofluthrin and information on related chemicals from the literature. The human relevance of the rat liver carcinogenic response is then discussed based upon the human relevance framework. Two-year treatment with high dose of Metofluthrin produced hepatocellular tumors in both sexes of the Wistar rats. Metofluthrin induced CYP2B (increased smooth endoplasmic reticulum), resulted in increased liver weights which were associated with centrilobular hepatocyte hypertrophy, and induction of increased hepatocellular DNA replications. The above parameters related to the key events in Metofluthrin-induced liver tumors were observed at or below tumorigenic dose levels. Furthermore, CYP2B induction by Metofluthrin was shown to involve activation of the constitutive androstane receptor in rat hepatocytes. Based on the evidence, including a comparison with the results with another chemical, phenobarbital, acting by a similar MOA, it is reasonable to conclude that Metofluthrin will not have any hepatocarcinogenic activity in humans.

  6. Distracted Biking: An Observational Study.

    Science.gov (United States)

    Wolfe, Elizabeth Suzanne; Arabian, Sandra Strack; Breeze, Janis L; Salzler, Matthew J

    2016-01-01

    Commuting via bicycle is a very popular mode of transportation in the Northeastern United States. Boston, MA, has seen a rapid increase in bicycle ridership over the past decade, which has raised concerns and awareness about bicycle safety. An emerging topic in this field is distracted bicycle riding. This study was conducted to provide descriptive data on the prevalence and type of distracted bicycling in Boston at different times of day. This was a cross-sectional study in which observers tallied bicyclists at 4 high traffic intersections in Boston during various peak commuting hours for 2 types of distractions: auditory (earbuds/phones in or on ears), and visual/tactile (electronic device or other object in hand). Nineteen hundred seventy-four bicyclists were observed and 615 (31.2%), 95% CI [29, 33%], were distracted. Of those observed, auditory distractions were the most common (N = 349; 17.7%), 95% CI [16, 19], p = .0003, followed by visual/tactile distractions (N = 266; 13.5%), 95% CI [12, 15]. The highest proportion (40.7%), 95% CI [35, 46], of distracted bicyclists was observed during the midday commute (between 13:30 and 15:00). Distracted bicycling is a prevalent safety concern in the city of Boston, as almost a third of all bicyclists exhibited distracted behavior. Education and public awareness campaigns should be designed to decrease distracted bicycling behaviors and promote bicycle safety in Boston. An awareness of the prevalence of distracted biking can be utilized to promote bicycle safety campaigns dedicated to decreasing distracted bicycling and to provide a baseline against which improvements can be measured.

  7. Safety goals and safety culture opening plenary. 2. Safety Regulation Implemented by Gosatomnadzor of Russia

    International Nuclear Information System (INIS)

    Gutsalov, A.T.; Bukrinsky, A.M.

    2001-01-01

    more strict than those recommended in the INSAG-3 and INSAG-12 reports, but they correlate with the value of negligible individual risk of 10 -6 , established in 'Radiation Safety Standards' (NRB-99) and consider still a high level of uncertainty in calculation of these probabilities. OPB- 88/97 also defines safety culture and principles of its formation and provision. Gosatomnadzor of Russia is a federal executive authority implementing state safety regulation in nuclear energy use. One of the main activities of Gosatomnadzor of Russia is nuclear and radiation safety regulation in sitting, design, construction, operation, and decommissioning of nuclear facilities. The activities include the following: 1. development and enactment of regulatory documents; 2. licensing of activities at nuclear facilities; 3. state supervision on observing the requirements of federal rules and regulations and license conditions. Gosatomnadzor of Russia strives toward solving the problems of consistent safety improvement of facilities and technologies up to the internationally accepted level, acting within the framework of the existing set of special safety rules and regulations in production and use of nuclear energy. Simultaneously, Gosatomnadzor of Russia develops proposals aimed at the improvement of legislative and regulatory bases of the Russian Federation as well as licensing and inspection procedures and implementing them. The main principles that Gosatomnadzor of Russia follows in its practical activities are openness, publicity, and cooperation with juridical and natural persons, whose activities are regulated with the purpose of achieving safety. This cooperation is accomplished in compliance with the principle of separation of responsibilities. According to this principle, the parties that are involved in activities related to the use of nuclear materials and nuclear energy on one hand, and in the state regulation of nuclear and radiation safety on the other hand, bear

  8. Radiological safety in petroleum industry. Towards prevention culture

    International Nuclear Information System (INIS)

    Truppa, Walter A.

    2007-01-01

    Within the frame of regulatory control of industrial applications the audit of sealed and open radioactive sources in oil uses is one of the most relevant. The handling of radioactive sources, the requirement of procedures and training are just a few examples among all those that make up the radiological safety culture. A number of requirements divided into three main groups: operational safety at the storage area of radioactive sources, during transportation and during the applications (Cementation, well logging and use of radiotracers) are highlighted. Due to the great number of aspects that have to be taken in account as well as the interrelation of all control processes it is highly recommended that aspects of safety culture and quality should be considered and improvements regarding prevention, should be introduced so as to correct deviations that could arise in order to avoid radiological risk situations, emphasizing risk perception situations, attitude training, implementation of audit and level of safety in the facilities and control of duties, involving radiological material handling, described in the present work. (author) [es

  9. HERBE final safety report; HERBE Finalni sigurnosni izvestaj

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1991-07-01

    The Final safety report of HERBE system constructed at the RB reactor consists of 13 chapters, as follows. Chapter 0 includes a summary and the contents of the Final safety report, fundamental characteristics of the system and conclusion remarks, with the license agreement of the Safety Committee of the Boris Kidric Institute. Chapter 1 describes and analyzes the site of the HERBE system, including demography, topography, meteorology, hydrology, geology, seismicity, ecology. Chapter 3 covers technical characteristics of the system, Chapter 4 deals with safety analysis, Chapter 5 describes organisation of construction and preliminary operational testing of the system. Chapter 6 deals with organisation and program of test and regular operation, relevant procedures. Chapter 7 defines operational conditions and constraints, Chapter 8 and describe methods and means of radiation protection and radioactive materials management respectively. Chapter 10 contains a review of emergency plans, measures and procedures for nuclear accident protection. Chapters 11 and 12 are concerned with quality assurance program and physical protection of the HERBE system and related nuclear material.

  10. Fourth national report of Brazil for the nuclear safety convention. Sep. 2007

    International Nuclear Information System (INIS)

    2007-09-01

    This Fourth National Report of Brazil is a new update to include relevant information of the period of 2004-2007. This document represents the national report prepared as a fulfillment of the brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations

  11. Fourth national report of Brazil for the nuclear safety convention. Sep. 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-09-15

    This Fourth National Report of Brazil is a new update to include relevant information of the period of 2004-2007. This document represents the national report prepared as a fulfillment of the brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations

  12. Lessons Learned from a Five-year Evaluation of the Belgian Safety Culture Oversight Process

    International Nuclear Information System (INIS)

    Bernard, B.

    2016-01-01

    The Belgian Regulatory Body has implemented a Safety Culture oversight process since 2010. In a nutshell, this process is based on field observations provided by inspectors or safety analysts during any contact with a licencee (inspections, meetings, phone calls, etc). These observations are recorded within an observation (excel) sheet—aiming at describing factual and contextual issues — and are linked to IAEA Safety Culture attributes. It should be stressed that the purpose of the process is not to give a comprehensive view of a licencee safety culture but to address findings that require attention or action on the part of a licencee. In other words, gathering safety culture observations aims at identifying cultural, organizational or behavioural issues in order to feed a regulatory response to potential problems. Safety Culture Observations (SCO) are then fully integrated in routine inspection activities and must be seen as an input of the overall oversight process. As a result, the assessment of the SCO is inserted within the yearly safety evaluation report performed by Bel V and transmitted to the licencee. However, observing safety culture is not a natural approach for engineers. Guidance, training and coaching must be provided in order to open up safety dimensions to be captured. In other words, a SCO process requires a continuous support in order to promote a holistic and systemic view of safety.

  13. Stimulus fear-relevance and the vicarious learning pathway to childhood fears.

    Science.gov (United States)

    Askew, Chris; Dunne, Güler; Özdil, Zehra; Reynolds, Gemma; Field, Andy P

    2013-10-01

    Enhanced fear learning for fear-relevant stimuli has been demonstrated in procedures with adults in the laboratory. Three experiments investigated the effect of stimulus fear-relevance on vicarious fear learning in children (aged 6-11 years). Pictures of stimuli with different levels of fear-relevance (flowers, caterpillars, snakes, worms, and Australian marsupials) were presented alone or together with scared faces. In line with previous studies, children's fear beliefs and avoidance preferences increased for stimuli they had seen with scared faces. However, in contrast to evidence with adults, learning was mostly similar for all stimulus types irrespective of fear-relevance. The results support a proposal that stimulus preparedness is bypassed when children observationally learn threat-related information from adults.

  14. Measuring patient safety in a UK dental hospital: development of a dental clinical effectiveness dashboard.

    Science.gov (United States)

    Pemberton, M N; Ashley, M P; Shaw, A; Dickson, S; Saksena, A

    2014-10-01

    Patient safety is an important marker of quality for any healthcare organisation. In 2008, the British Government white paper entitled High quality care for all, resulting from a review led by Lord Darzi, identified patient safety as a key component of quality and discussed how it might be measured, analysed and acted upon. National and local clinically curated metrics were suggested, which could be displayed via a 'clinical dashboard'. This paper explains the development of a clinical effectiveness dashboard focused on patient safety in an English dental hospital and how it has helped us identify relevant patient safety issues in secondary dental care.

  15. Technical Guidance from the International Safety Framework for Nuclear Power Source Applications in Outer Space for Design and Development Phases

    Science.gov (United States)

    Summerer, Leopold

    2014-08-01

    In 2009, the International Safety Framework for Nuclear Power Source Applications in Outer Space [1] has been adopted, following a multi-year process that involved all major space faring nations in the frame of the International Atomic Energy Agency and the UN Committee on the Peaceful Uses of Outer Space. The safety framework reflects an international consensus on best practices. After the older 1992 Principles Relevant to the Use of Nuclear Power Sources in Outer Space, it is the second document at UN level dedicated entirely to space nuclear power sources.This paper analyses aspects of the safety framework relevant for the design and development phases of space nuclear power sources. While early publications have started analysing the legal aspects of the safety framework, its technical guidance has not yet been subject to scholarly articles. The present paper therefore focuses on the technical guidance provided in the safety framework, in an attempt to assist engineers and practitioners to benefit from these.

  16. Do safety checklists improve teamwork and communication in the operating room? A systematic review.

    Science.gov (United States)

    Russ, Stephanie; Rout, Shantanu; Sevdalis, Nick; Moorthy, Krishna; Darzi, Ara; Vincent, Charles

    2013-12-01

    The aim of this systematic review was to assess the impact of surgical safety checklists on the quality of teamwork and communication in the operating room (OR). Safety checklists have been shown to impact positively on patient morbidity and mortality following surgery, but it is unclear whether this clinical improvement is related to an improvement in OR teamwork and communication. A systematic search strategy of MEDLINE, EMBASE, PsycINFO, Google Scholar, and the Cochrane Database for Systematic Reviews was undertaken to obtain relevant articles. After de-duplication and the addition of limits, 315 articles were screened for inclusion by 2 researchers and all articles meeting a set of prespecified inclusion criteria were retained. Information regarding the type of checklist, study design, assessment tools used, outcomes, and study limitations was extracted. Twenty articles formed the basis of this systematic review. All articles described an empirical study relating to a case-specific safety checklist for surgery as the primary intervention, with some measure of change/improvement in teamwork and/or communication relating to its use. The methods for assessing teamwork and communication varied greatly, including surveys, observations, interviews, and 360° assessments. The evidence suggests that safety checklists improve the perceived quality of OR teamwork and communication and reduce observable errors relating to poor team skills. This is likely to function through establishing an open platform for communication at the start of a procedure: encouraging the sharing of critical case-related information, promoting team coordination and decision making, flagging knowledge gaps, and enhancing team cohesion. However, the evidence would also suggest that when used suboptimally or when individuals have not bought in to the process, checklists may conversely have a negative impact on the function of the team. Safety checklists are beneficial for OR teamwork and

  17. Basic Safety Standards for Radiation Protection

    International Nuclear Information System (INIS)

    1962-01-01

    Pursuant to the provisions of its Statute relevant to the adoption and application of safety standards for protection against radiation, the Agency convened a panel of experts which formulated the Basic Safety Standards set forth in this publication. The panel met under the chairmanship of Professor L. Bugnard, Director of the French Institut National d'Hygiene, and representatives of the United Nations and of several of its specialized agencies participated in its work. The Basic Safety Standards thus represent the result of a most careful assessment of the variety of complex scientific and administrative problems involved. Nevertheless, of course, they will need to be revised from time to time in the light of advances in scientific knowledge, of comments received from Member States and of the work of other competent international organizations. The Agency's Board of Governors in June 1962 approved the Standards as a first edition, subject to later revision as mentioned above, and authorized Director General Sigvard Eklund to apply the Standards in Agency and Agency-assisted operations and to invite Governments of Member States to take them as a basis in formulating national regulations or recommendations on protection against the dangers arising from ionizing radiations. It is mainly for this last purpose that the Basic Safety Standards are now being published in the Safety Series; but it is hoped that this publication will also interest a much wider circle of readers.

  18. Radiation safety and regulatory aspects in Medical Facilities

    International Nuclear Information System (INIS)

    Banerjee, Sharmila

    2017-01-01

    Radiation safety and regulatory aspect of medical facilities are relevant in the context where radiation is used in providing healthcare to human patients. These include facilities, which carry out radiological procedures in diagnostic radiology, including dentistry, image-guided interventional procedures, nuclear medicine, and radiation therapy. The safety regulations provide recommendations and guidance on meeting the requirements for the safe use of radiation in medicine. The different safety aspects which come under its purview are the personnel involved in medical facilities where radiological procedures are performed which include the medical practitioners, radiation technologists, medical physicists, radiopharmacists, radiation protection and over and above all the patients. Regulatory aspects cover the guidelines provided by ethics committees, which regulate the administration of radioactive formulation in human patients. Nuclear medicine is a modality that utilizes radiopharmaceuticals either for diagnosis of physiological disorders related to anatomy, physiology and patho-physiology and for diagnosis and treatment of cancer

  19. Nuclear Reactor RA Safety Report, Format and Contents

    International Nuclear Information System (INIS)

    1986-11-01

    This is a new complete version of the safety report of nuclear reactor RA is made according to the recommendations of the IAEA. Report includes all the relevant data needed for evaluation of safe operation of this nuclear facility. Each of seven volumes of this report cover separate topics as follows: (1) introduction; (2) Site characteristics; (3) description of the reactor building and installations; (4) description of the reactor; (5) description of the coolant system; (6) description of the regulation and safety instrumentation; (7) description of the power supply system; (8) description of the auxiliary systems; (9) radiation protection issues; (10) radioactive waste management (11) reactor operation; (12) accident analysis during previous operation; (13) analysis of possible accident causes; (14) safety analysis and preventive actions: (15) analysis of significant accidents; (16) analysis of maximum possible accident; (17) environmental impact analysis in case of accident [sr

  20. Most common road safety engineering deficiencies in South Eastern Europe as a part of safe system approach

    Science.gov (United States)

    Jovanov, D.; Vollpracht, H. J.; Beles, H.; Popa, V.; Tolea, B. A.

    2017-10-01

    Most common road safety engineering deficiencies identified by the authors in South Eastern Europe, including Romania, have been collected together and presented in this paper as a part of road safety unbreakably connected to the safe system approach (driver-vehicle-road). In different South Eastern Europe countries Road Safety Audit (RSA), Road Safety Inspection (RSI), as well as Black Spot Management (BSM) was introduced and practical implementation experience enabled the authors to analyze the road safety problems. Typical road safety engineering deficiencies have been presented in 8 different subsections, based on PIARC (World Road Association) RSA approach. This paper presents collected common road safety problems with relevant illustrations (real pictures) with associated accident risks.