WorldWideScience

Sample records for integrated vehicle-based safety

  1. Integrated vehicle-based safety systems light-vehicle field operational test key findings report.

    Science.gov (United States)

    2011-01-01

    "This document presents key findings from the light-vehicle field operational test conducted as part of the Integrated Vehicle-Based Safety Systems program. These findings are the result of analyses performed by the University of Michigan Transportat...

  2. Integrated vehicle-based safety systems light-vehicle field operational test, methodology and results report.

    Science.gov (United States)

    2010-12-01

    "This document presents the methodology and results from the light-vehicle field operational test conducted as part of the Integrated Vehicle-Based Safety Systems program. These findings are the result of analyses performed by the University of Michi...

  3. Integrated vehicle-based safety systems (IVBSS) : light vehicle platform field operational test data analysis plan.

    Science.gov (United States)

    2009-12-22

    This document presents the University of Michigan Transportation Research Institutes plan to : perform analysis of data collected from the light vehicle platform field operational test of the : Integrated Vehicle-Based Safety Systems (IVBSS) progr...

  4. Integrated vehicle-based safety systems (IVBSS) : heavy truck platform field operational test data analysis plan.

    Science.gov (United States)

    2009-11-23

    This document presents the University of Michigan Transportation Research Institutes plan to perform : analysis of data collected from the heavy truck platform field operational test of the Integrated Vehicle- : Based Safety Systems (IVBSS) progra...

  5. Integrated development of light armored vehicles based on wargaming simulators

    Science.gov (United States)

    Palmarini, Marc; Rapanotti, John

    2004-08-01

    Vehicles are evolving into vehicle networks through improved sensors, computers and communications. Unless carefully planned, these complex systems can result in excessive crew workload and difficulty in optimizing the use of the vehicle. To overcome these problems, a war-gaming simulator is being developed as a common platform to integrate contributions from three different groups. The simulator, OneSAF, is used to integrate simplified models of technology and natural phenomena from scientists and engineers with tactics and doctrine from the military and analyzed in detail by operations analysts. This approach ensures the modelling of processes known to be important regardless of the level of information available about the system. Vehicle survivability can be improved as well with better sensors, computers and countermeasures to detect and avoid or destroy threats. To improve threat detection and reliability, Defensive Aids Suite (DAS) designs are based on three complementary sensor technologies including: acoustics, visible and infrared optics and radar. Both active armour and softkill countermeasures are considered. In a typical scenario, a search radar, providing continuous hemispherical coverage, detects and classifies the threat and cues a tracking radar. Data from the tracking radar is processed and an explosive grenade is launched to destroy or deflect the threat. The angle of attack and velocity from the search radar can be used by the soft-kill system to carry out an infrared search and track or an illuminated range-gated scan for the threat platform. Upon detection, obscuration, countermanoeuvres and counterfire can be used against the threat. The sensor suite is completed by acoustic detection of muzzle blast and shock waves. Automation and networking at the platoon level contribute to improved vehicle survivability. Sensor data fusion is essential in avoiding catastrophic failure of the DAS. The modular DAS components can be used with Light Armoured

  6. Research on Heat Dissipation of Electric Vehicle Based on Safety Architecture Optimization

    Science.gov (United States)

    Zhou, Chao; Guo, Yajuan; Huang, Wei; Jiang, Haitao; Wu, Liwei

    2017-10-01

    In order to solve the problem of excessive temperature in the discharge process of lithium-ion battery and the temperature difference between batteries, a heat dissipation of electric vehicle based on safety architecture optimization is designed. The simulation is used to optimize the temperature field of the heat dissipation of the battery. A reasonable heat dissipation control scheme is formulated to achieve heat dissipation requirements. The results show that the ideal working temperature range of the lithium ion battery is 20?∼45?, and the temperature difference between the batteries should be controlled within 5?. A cooling fan is arranged at the original air outlet of the battery model, and the two cooling fans work in turn to realize the reciprocating flow. The temperature difference is controlled within 5? to ensure the good temperature uniformity between the batteries of the electric vehicle. Based on the above finding, it is concluded that the heat dissipation design for electric vehicle batteries is safe and effective, which is the most effective methods to ensure battery life and vehicle safety.

  7. Safety Performance Evaluations for the Vehicle Based Movable Barriers Using Full Scale Crash Tests

    Directory of Open Access Journals (Sweden)

    Jin Minsoo

    2017-01-01

    Full Text Available The present study aims to develop a prototype of large-size movable barriers to protect roadside workers from incoming vehicles to the road work area with the following functions: maximization of work space in the right and left directions, convenient mobility, and minimization of impact without modification of the inside of movable barriers into traffic lanes and perform safety performance assessment on passengers through full scale crash tests. The large movable barrier was divided into folder type and telescope type and the development stage was now at the prototype phase. A full scale crash test was conducted prior to certification test at a level of 90%. The full scale crash test result showed that both types of folder type movable barrier and telescope type movable barrier satisfied the standard of the passenger safety performance evaluation at a level of 90%.

  8. Integrated Safety in ''SARAF'

    International Nuclear Information System (INIS)

    Dickstein, P.; Grof, Y.; Machlev, M.; Pernick, A.

    2004-01-01

    As of the very early stages of the accelerator project at the Soreq Nuclear Research Center ''SARAF'' a safety group was established which has been an inseparable participant in the planning and design of the new facility. The safety group comprises of teams responsible for the shielding, radiation protection and general industrial safety aspects of ''SARAF''. The safety group prepared and documented the safety envelope for the accelerator, dealing with the safety requirements and guidelines for the first, pre-operational, stages of the project. The safety envelope, though based upon generic principles, took into account the accelerator features and the expected modes of operation. The safety envelope was prepared in a hierarchical structure, containing Basic Principles, Basic Guidelines, General Principles for Safety Implementation, Safety Requirements and Safety Underlining Issues. The above safety envelope applies to the entire facility, which entails the accelerator itself and the experimental areas and associated plant and equipment utilizing and supporting the production of the accelerated particle beams

  9. Integrated Safety in Design

    DEFF Research Database (Denmark)

    Schultz, Casper Siebken; Jørgensen, Kirsten

    2014-01-01

    An on-going research project investigates the inclusion of health and safety considerations in the design phase as a means to achieve a higher level of health and safety in the construction industry. Moreover, the approach is coupled to the overall quality efforts. Two architectural firms and two...... consulting engineering firms are project participants. The hypothesis is that health and safety problems in execution can be prevented through better planning in the early stages of the construction processes and that accidents are prevented by providing safety. In the first stage of the research project...... a theoretical framework is developed from a combination of existing literature on health and safety and a mapping of existing practices based on interviews in all four companies. The interviews revealed that the basic knowledge on OHS among architects and engineers is limited. Also currently designers typically...

  10. Integral fast reactor safety features

    International Nuclear Information System (INIS)

    Cahalan, J.E.; Kramer, J.M.; Marchaterre, J.F.; Mueller, C.J.; Pedersen, D.R.; Sevy, R.H.; Wade, D.C.; Wei, T.Y.C.

    1988-01-01

    The Integral Fast Reactor (IFR) is an advanced liquid-metal-cooled reactor concept being developed at Argonne National Laboratory. The two major goals of the IFR development effort are improved economics and enhanced safety. In addition to liquid metal cooling, the principal design features that distinguish the IFR are: (1) a pool-type primary system, (2) an advanced ternary alloy metallic fuel, and (3) an integral fuel cycle with on-site fuel reprocessing and fabrication. This paper focuses on the technical aspects of the improved safety margins available in the IFR concept. This increased level of safety is made possible by (1) the liquid metal (sodium) coolant and pool-type primary system layout, which together facilitate passive decay heat removal, and (2) a sodium-bonded metallic fuel pin design with thermal and neutronic properties that provide passive core responses which control and mitigate the consequences of reactor accidents

  11. Integral fast reactor safety features

    International Nuclear Information System (INIS)

    Cahalan, J.E.; Kramer, J.M.; Marchaterre, J.F.; Mueller, C.J.; Pedersen, D.R.; Sevy, R.H.; Wade, D.C.; Wei, T.Y.C.

    1988-01-01

    The integral fast reactor (IFR) is an advanced liquid-metal-cooled reactor concept being developed at Argonne National Laboratory. The two major goals of the IFR development effort are improved economics and enhanced safety. In addition to liquid metal cooling, the principal design features that distinguish the IFR are: a pool-type primary system, and advanced ternary alloy metallic fuel, and an integral fuel cycle with on-site fuel reprocessing and fabrication. This paper focuses on the technical aspects of the improved safety margins available in the IFR concept. This increased level of safety is made possible by the liquid metal (sodium) coolant and pool-type primary system layout, which together facilitate passive decay heat removal, and a sodium-bonded metallic fuel pin design with thermal and neutronic properties that provide passive core responses which control and mitigate the consequences of reactor accidents

  12. Safety in Schools: An Integral Approach

    Science.gov (United States)

    Gairin, Joaquin; Castro, Diego

    2011-01-01

    The present paper summarizes a research project into integral safety in schools. The aims of this particular research are, firstly, to evaluate the degree of integral safety in schools, secondly, to propose means for improving prevention and integral safety systems and thirdly, to identify the characteristics of safety culture. The field work was…

  13. Integrated therapy safety management system.

    Science.gov (United States)

    Podtschaske, Beatrice; Fuchs, Daniela; Friesdorf, Wolfgang

    2013-09-01

    The aim is to demonstrate the benefit of the medico-ergonomic approach for the redesign of clinical work systems. Based on the six layer model, a concept for an 'integrated therapy safety management' is drafted. This concept could serve as a basis to improve resilience. The concept is developed through a concept-based approach. The state of the art of safety and complexity research in human factors and ergonomics forms the basis. The findings are synthesized to a concept for 'integrated therapy safety management'. The concept is applied by way of example for the 'medication process' to demonstrate its practical implementation. The 'integrated therapy safety management' is drafted in accordance with the six layer model. This model supports a detailed description of specific work tasks, the corresponding responsibilities and related workflows at different layers by using the concept of 'bridge managers'. 'Bridge managers' anticipate potential errors and monitor the controlled system continuously. If disruptions or disturbances occur, they respond with corrective actions which ensure that no harm results and they initiate preventive measures for future procedures. The concept demonstrates that in a complex work system, the human factor is the key element and final authority to cope with the residual complexity. The expertise of the 'bridge managers' and the recursive hierarchical structure results in highly adaptive clinical work systems and increases their resilience. The medico-ergonomic approach is a highly promising way of coping with two complexities. It offers a systematic framework for comprehensive analyses of clinical work systems and promotes interdisciplinary collaboration. © 2013 The Authors. British Journal of Clinical Pharmacology © 2013 The British Pharmacological Society.

  14. Integrated therapy safety management system

    Science.gov (United States)

    Podtschaske, Beatrice; Fuchs, Daniela; Friesdorf, Wolfgang

    2013-01-01

    Aims The aim is to demonstrate the benefit of the medico-ergonomic approach for the redesign of clinical work systems. Based on the six layer model, a concept for an ‘integrated therapy safety management’ is drafted. This concept could serve as a basis to improve resilience. Methods The concept is developed through a concept-based approach. The state of the art of safety and complexity research in human factors and ergonomics forms the basis. The findings are synthesized to a concept for ‘integrated therapy safety management’. The concept is applied by way of example for the ‘medication process’ to demonstrate its practical implementation. Results The ‘integrated therapy safety management’ is drafted in accordance with the six layer model. This model supports a detailed description of specific work tasks, the corresponding responsibilities and related workflows at different layers by using the concept of ‘bridge managers’. ‘Bridge managers’ anticipate potential errors and monitor the controlled system continuously. If disruptions or disturbances occur, they respond with corrective actions which ensure that no harm results and they initiate preventive measures for future procedures. The concept demonstrates that in a complex work system, the human factor is the key element and final authority to cope with the residual complexity. The expertise of the ‘bridge managers’ and the recursive hierarchical structure results in highly adaptive clinical work systems and increases their resilience. Conclusions The medico-ergonomic approach is a highly promising way of coping with two complexities. It offers a systematic framework for comprehensive analyses of clinical work systems and promotes interdisciplinary collaboration. PMID:24007448

  15. An integrative model of organizational safety behavior.

    Science.gov (United States)

    Cui, Lin; Fan, Di; Fu, Gui; Zhu, Cherrie Jiuhua

    2013-06-01

    This study develops an integrative model of safety management based on social cognitive theory and the total safety culture triadic framework. The purpose of the model is to reveal the causal linkages between a hazardous environment, safety climate, and individual safety behaviors. Based on primary survey data from 209 front-line workers in one of the largest state-owned coal mining corporations in China, the model is tested using structural equation modeling techniques. An employee's perception of a hazardous environment is found to have a statistically significant impact on employee safety behaviors through a psychological process mediated by the perception of management commitment to safety and individual beliefs about safety. The integrative model developed here leads to a comprehensive solution that takes into consideration the environmental, organizational and employees' psychological and behavioral aspects of safety management. Copyright © 2013 National Safety Council and Elsevier Ltd. All rights reserved.

  16. Integrated Safety Culture Model and Application

    Institute of Scientific and Technical Information of China (English)

    汪磊; 孙瑞山; 刘汉辉

    2009-01-01

    A new safety culture model is constructed and is applied to analyze the correlations between safety culture and SMS. On the basis of previous typical definitions, models and theories of safety culture, an in-depth analysis on safety culture's structure, composing elements and their correlations was conducted. A new definition of safety culture was proposed from the perspective of sub-cuhure. 7 types of safety sub-culture, which are safety priority culture, standardizing culture, flexible culture, learning culture, teamwork culture, reporting culture and justice culture were defined later. Then integrated safety culture model (ISCM) was put forward based on the definition. The model divided safety culture into intrinsic latency level and extrinsic indication level and explained the potential relationship between safety sub-culture and all safety culture dimensions. Finally in the analyzing of safety culture and SMS, it concluded that positive safety culture is the basis of im-plementing SMS effectively and an advanced SMS will improve safety culture from all around.

  17. 10 CFR 70.62 - Safety program and integrated safety analysis.

    Science.gov (United States)

    2010-01-01

    ...; (iv) Potential accident sequences caused by process deviations or other events internal to the... have experience in nuclear criticality safety, radiation safety, fire safety, and chemical process... this safety program; namely, process safety information, integrated safety analysis, and management...

  18. Bibliography for computer security, integrity, and safety

    Science.gov (United States)

    Bown, Rodney L.

    1991-01-01

    A bibliography of computer security, integrity, and safety issues is given. The bibliography is divided into the following sections: recent national publications; books; journal, magazine articles, and miscellaneous reports; conferences, proceedings, and tutorials; and government documents and contractor reports.

  19. Preliminary Integrated Safety Analysis Status Report

    International Nuclear Information System (INIS)

    Gwyn, D.

    2001-01-01

    This report provides the status of the potential Monitored Geologic Repository (MGR) Integrated Safety Analysis (EA) by identifying the initial work scope scheduled for completion during the ISA development period, the schedules associated with the tasks identified, safety analysis issues encountered, and a summary of accomplishments during the reporting period. This status covers the period from October 1, 2000 through March 30, 2001

  20. Developing an integrated dam safety program

    International Nuclear Information System (INIS)

    Nielsen, N. M.; Lampa, J.

    1996-01-01

    An effort has been made to demonstrate that dam safety is an integral part of asset management which, when properly done, ensures that all objectives relating to safety and compliance, profitability, stakeholders' expectations and customer satisfaction, are achieved. The means to achieving this integration of the dam safety program and the level of effort required for each core function have been identified using the risk management approach to pinpoint vulnerabilities, and subsequently to focus priorities. The process is considered appropriate for any combination of numbers, sizes and uses of dams, and is designed to prevent exposure to unacceptable risks. 5 refs., 1 tab

  1. Psychological Safety During Military Integrations

    NARCIS (Netherlands)

    Wermser, Frederik; Täuber, Susanne; Essens, Peter; Molleman, Henricus; Beeres, Robert; Bakx, Gwendolyn; de Waard, Erik; Rietjens, Sebastiaan

    Increased military cooperation between member states of the European Union is a political given. The Netherlands and Germany form a spearhead in this process by integrating entire military units (i.e., brigades, battalions, companies) into higher-order units of the respective other nation (i.e.,

  2. Oswer integrated health and safety standard operating practices. Directive

    International Nuclear Information System (INIS)

    1993-02-01

    The directive implements the OSWER (Office of Solid Waste and Emergency Response) Integrated Health and Safety Standards Operating Practices in conjunction with the OSHA (Occupational Safety and Health Act) Worker Protection Standards, replacing the OSWER Integrated Health and Safety Policy

  3. Integrated Deterministic-Probabilistic Safety Assessment Methodologies

    Energy Technology Data Exchange (ETDEWEB)

    Kudinov, P.; Vorobyev, Y.; Sanchez-Perea, M.; Queral, C.; Jimenez Varas, G.; Rebollo, M. J.; Mena, L.; Gomez-Magin, J.

    2014-02-01

    IDPSA (Integrated Deterministic-Probabilistic Safety Assessment) is a family of methods which use tightly coupled probabilistic and deterministic approaches to address respective sources of uncertainties, enabling Risk informed decision making in a consistent manner. The starting point of the IDPSA framework is that safety justification must be based on the coupling of deterministic (consequences) and probabilistic (frequency) considerations to address the mutual interactions between stochastic disturbances (e.g. failures of the equipment, human actions, stochastic physical phenomena) and deterministic response of the plant (i.e. transients). This paper gives a general overview of some IDPSA methods as well as some possible applications to PWR safety analyses. (Author)

  4. Integral fast reactor concept inherent safety features

    International Nuclear Information System (INIS)

    Marchaterre, J.F.; Sevy, R.H.; Cahalan, J.E.

    1987-01-01

    The Integral Fast Reactor (IFR) is an innovative liquid-metal-cooled reactor concept being developed at Argonne National Laboratory. The two major goals of the IFT development effort are improved economics and enhanced safety. The design features that together fulfill these goals are: 1) a liquid metal (sodium) coolant, 2) a pool-type reactor primary system configuration, 3) an advanced ternary alloy metallic fuel, and 4) an integral fuel cycle. This paper reviews the design features that contribute to the safety margins inherent to the IFR concept. Special emphasis is placed on the ability of the IFR design to accommodate anticipated transients without scram (ATWS)

  5. Integral Fast Reactor concept inherent safety features

    International Nuclear Information System (INIS)

    Marchaterre, J.F.; Sevy, R.H.; Cahalan, J.E.

    1986-01-01

    The Integral Fast Reactor (IFR) is an innovative liquid-metal-cooled reactor concept being developed at Argonne National Laboratory. The two major goals of the IFR development effort are improved economics and enhanced safety. The design features that together fulfill these goals are: (1) a liquid metal (sodium) coolant, (2) a pool-type reactor primary system configuration, (3) an advanced ternary alloy metallic fuel, and (4) an integral fuel cycle. This paper reviews the design features that contribute to the safety margins inherent to the IFR concept. Special emphasis is placed on the ability of the IFR design to accommodate anticipated transients without scram (ATWS)

  6. Behavioral integrity for safety, priority of safety, psychological safety, and patient safety : a team-level study

    NARCIS (Netherlands)

    Leroy, H.; Dierynck, B.; Anseel, F.; Simons, T.; Halbesleben, J.R.; McCaughey, D.; Savage, G.T.; Sels, L.

    2012-01-01

    This article clarifies how leader behavioral integrity for safety helps solve follower's double bind between adhering to safety protocols and speaking up about mistakes against protocols. Path modeling of survey data in 54 nursing teams showed that head nurse behavioral integrity for safety

  7. Analysis of Vehicle-Based Security Operations

    Energy Technology Data Exchange (ETDEWEB)

    Carter, Jason M [ORNL; Paul, Nate R [ORNL

    2015-01-01

    Vehicle-to-vehicle (V2V) communications promises to increase roadway safety by providing each vehicle with 360 degree situational awareness of other vehicles in proximity, and by complementing onboard sensors such as radar or camera in detecting imminent crash scenarios. In the United States, approximately three hundred million automobiles could participate in a fully deployed V2V system if Dedicated Short-Range Communication (DSRC) device use becomes mandatory. The system s reliance on continuous communication, however, provides a potential means for unscrupulous persons to transmit false data in an attempt to cause crashes, create traffic congestion, or simply render the system useless. V2V communications must be highly scalable while retaining robust security and privacy preserving features to meet the intra-vehicle and vehicle-to-infrastructure communication requirements for a growing vehicle population. Oakridge National Research Laboratory is investigating a Vehicle-Based Security System (VBSS) to provide security and privacy for a fully deployed V2V and V2I system. In the VBSS an On-board Unit (OBU) generates short-term certificates and signs Basic Safety Messages (BSM) to preserve privacy and enhance security. This work outlines a potential VBSS structure and its operational concepts; it examines how a vehicle-based system might feasibly provide security and privacy, highlights remaining challenges, and explores potential mitigations to address those challenges. Certificate management alternatives that attempt to meet V2V security and privacy requirements have been examined previously by the research community including privacy-preserving group certificates, shared certificates, and functional encryption. Due to real-world operational constraints, adopting one of these approaches for VBSS V2V communication is difficult. Timely misbehavior detection and revocation are still open problems for any V2V system. We explore the alternative approaches that may be

  8. Integrated framework for dynamic safety analysis

    International Nuclear Information System (INIS)

    Kim, Tae Wan; Karanki, Durga R.

    2012-01-01

    In the conventional PSA (Probabilistic Safety Assessment), detailed plant simulations by independent thermal hydraulic (TH) codes are used in the development of accident sequence models. Typical accidents in a NPP involve complex interactions among process, safety systems, and operator actions. As independent TH codes do not have the models of operator actions and full safety systems, they cannot literally simulate the integrated and dynamic interactions of process, safety systems, and operator responses. Offline simulation with pre decided states and time delays may not model the accident sequences properly. Moreover, when stochastic variability in responses of accident models is considered, defining all the combinations for simulations will be cumbersome task. To overcome some of these limitations of conventional safety analysis approach, TH models are coupled with the stochastic models in the dynamic event tree (DET) framework, which provides flexibility to model the integrated response due to better communication as all the accident elements are in the same model. The advantages of this framework also include: Realistic modeling in dynamic scenarios, comprehensive results, integrated approach (both deterministic and probabilistic models), and support for HRA (Human Reliability Analysis)

  9. IGSC - Integration Group for the Safety Case

    International Nuclear Information System (INIS)

    2015-01-01

    Countries that rely on nuclear energy and materials have an ethical obligation to manage radioactive waste in a safe and environmentally responsible manner. For society to support the sustainable solutions envisaged, disposal concepts must be technologically sound and the safety of these concepts must be convincingly demonstrated. The Nuclear Energy Agency's Integration Group for the Safety Case (IGSC) establishes and documents the technical and scientific basis for developing and reviewing safety cases as a platform for dialogue among technical experts and as a tool for decision making. The IGSC addresses various strategic and policy aspects of radioactive waste management as the technical advisory body to the NEA Radioactive Waste Management Committee (RWMC) for all issues related to repository development. For more than two decades, the IGSC and its predecessor technical groups have promoted the exchange of national experience in evaluating and implementing geological repositories. IGSC activities foster consensus on best practices and encourage the development of innovative, advanced approaches covering the technical aspects at all stages of repository implementation, including: - strategies to characterise and evaluate potential disposal sites; - methods to design and test engineered barrier systems; - priorities for research and development programmes to improve the understanding of important processes and interactions; - tools for safety assessments; - techniques for the effective presentation and communication of the results of safety cases and other factors that provide the basis for increased confidence in the safety of geological disposal facilities. The IGSC has been instrumental in further developing the 'modern safety case', a concept that originally emerged from NEA work in the 1990's. Cooperation with the International Atomic Energy Agency (IAEA) and the European Commission (EC) has led to the worldwide adoption of this safety

  10. K West integrated water treatment system subproject safety analysis document

    International Nuclear Information System (INIS)

    SEMMENS, L.S.

    1999-01-01

    This Accident Analysis evaluates unmitigated accident scenarios, and identifies Safety Significant and Safety Class structures, systems, and components for the K West Integrated Water Treatment System

  11. K West integrated water treatment system subproject safety analysis document

    Energy Technology Data Exchange (ETDEWEB)

    SEMMENS, L.S.

    1999-02-24

    This Accident Analysis evaluates unmitigated accident scenarios, and identifies Safety Significant and Safety Class structures, systems, and components for the K West Integrated Water Treatment System.

  12. Integration, differentiation and ambiguity in safety cultures

    DEFF Research Database (Denmark)

    Richter, Anne; Koch, Christian

    2004-01-01

    This article discusses safety cultures, drawing on the differentiation, integration and ambiguity-scheme introduced by scholars of organizational culture. An ethnographic approach has been applied in the study of meaning and symbols relating to work, hazards, occupational accidents and prevention....... The application of this approach is demonstrated through a multifacetted analysis of safety cultures. Case studies in Danish manufacturing show that it usually is necessary to differentiate between several safety cultures dispersed throughout the shop floor and other parts of the manufacturing organization....... Although some common elements are present across cultures, they are indeed a multiple configuration of cultures. The article illustrates this by providing one case showing a configuration of three cultures, metaphorically labelled Production, Welfare and Master. For example, the former views risk...

  13. Development of safety analysis technology for integral reactor; evaluation on safety concerns of integral reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hee Chul; Kim, Woong Sik; Lee, J. H. [Korea Institute of Nuclear Safety, Taejeon (Korea)

    2002-03-01

    The Nuclear Desalination Plant (NDP) is being developed to produce electricity and fresh water, and is expected to locate near population zone. In the aspect of safety, it is required to protect the public and environment from the possible releases of fission products and to prevent the fresh water from the contamination of radioactivity. Thus, in this study, the safety characteristics of the integral reactor adopting passive and inherent safety features significantly different from existing nuclear power plants were investigated. Also, safety requirements applicable to the NDP were analyzed based on the regulatory requirements for current light water reactor and advanced reactor designs, and user requirements for small-medium size reactors. Based on these analyses, some safety concerns to be considered in the design stage have been identified and discussed. They include the use of proven technology for new safety features, systematic event classification and selection, strengthening containment function, and the safety impacts on desalination-related systems. The study presents the general safety requirements applicable to licensing of an integral reactor and suggests additional regulatory requirements, which need to be developed, based on the direction to resolution of the safety concerns. The efforts to identify and technically resolve the safety concerns in the design stage will provide the early confidence of SMART safety and the technical basis to evaluate the safety to designers and reviewers in the future. Suggestion on the development of additional regulatory requirements will contribute for the regulator to taking actions for licensing of an integral reactor. 66 refs., 5 figs., 24 tabs. (Author)

  14. Integrated environment, safety, and health management system description

    International Nuclear Information System (INIS)

    Zoghbi, J. G.

    2000-01-01

    The Integrated Environment, Safety, and Health Management System Description that is presented in this document describes the approach and management systems used to address integrated safety management within the Richland Environmental Restoration Project

  15. Passive safety systems for integral reactors

    International Nuclear Information System (INIS)

    Kuul, V.S.; Samoilov, O.B.

    1996-01-01

    In this paper, a wide range of passive safety systems intended for use on integral reactors is considered. The operation of these systems relies on natural processes and does not require external power supplies. Using these systems, there is the possibility of preventing serious consequences for all classes of accidents including reactivity, loss-of-coolant and loss of heat sink as well as severe accidents. Enhancement of safety system reliability has been achieved through the use of self-actuating devices, capable of providing passive initiation of protective and isolation systems, which respond immediately to variations in the physical parameters of the fluid in the reactor or in a guard vessel. For beyond design base accidents accompanied by complete loss of heat removal capability, autonomous self-actuated ERHR trains have been proposed. These trains are completely independent of the secondary loops and need no action to isolate them from the steam turbine plant. Passive safety principles have been consistently implemented in AST-500, ATETS-200 and VPBER 600 which are new generation NPPs developed by OKBM. Their main characteristic is enhanced stability over a wide range of internal and external emergency initiators. (author). 10 figs

  16. Passive safety systems for integral reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kuul, V S; Samoilov, O B [OKB Mechanical Engineering (Russian Federation)

    1996-12-01

    In this paper, a wide range of passive safety systems intended for use on integral reactors is considered. The operation of these systems relies on natural processes and does not require external power supplies. Using these systems, there is the possibility of preventing serious consequences for all classes of accidents including reactivity, loss-of-coolant and loss of heat sink as well as severe accidents. Enhancement of safety system reliability has been achieved through the use of self-actuating devices, capable of providing passive initiation of protective and isolation systems, which respond immediately to variations in the physical parameters of the fluid in the reactor or in a guard vessel. For beyond design base accidents accompanied by complete loss of heat removal capability, autonomous self-actuated ERHR trains have been proposed. These trains are completely independent of the secondary loops and need no action to isolate them from the steam turbine plant. Passive safety principles have been consistently implemented in AST-500, ATETS-200 and VPBER 600 which are new generation NPPs developed by OKBM. Their main characteristic is enhanced stability over a wide range of internal and external emergency initiators. (author). 10 figs.

  17. Research on Integration of NPP Operational Safety Management Performance Systems

    International Nuclear Information System (INIS)

    Chi, Miao; Shi, Liping

    2014-01-01

    The operational safety management of Nuclear Power Plants demands systematic planning and integrated control. NPPs are following the well-developed safety indicator systems proposed by IAEA Operational Safety Performance Indicator Programme, NRC Reactor Oversight Process or the other institutions. Integration of the systems is proposed to benefiting from the advantages of both systems and avoiding improper application into the real world. The authors analyzed the possibility and necessity for system integration, and propose an indicator system integrating method

  18. INTEGRATED SAFETY MANAGEMENT SYSTEM IN AIR TRAFFIC SERVICES

    Directory of Open Access Journals (Sweden)

    Volodymyr Kharchenko

    2014-06-01

    Full Text Available The article deals with the analysis of the researches conducted in the field of safety management systems.Safety management system framework, methods and tools for safety analysis in Air Traffic Control have been reviewed.Principles of development of Integrated safety management system in Air Traffic Services have been proposed.

  19. NRU licence extension via integrated safety review

    Energy Technology Data Exchange (ETDEWEB)

    Mantifel, N. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

    2014-07-01

    The National Research Reactor, NRU at AECL Chalk River Laboratories achieved first criticality in November 1957. The completion of an Integrated Safety Review (ISR) in 2011, and subsequent Global Assessment Report (GAR), and Integrated Implementation Plan (IIP) has given confidence in the safe and reliable operation of NRU, therefore extending the licensing case to safely and reliably operate NRU until 2021 and beyond (64+ years of operation). The key vehicle to achieve this confidence is the IIP, that resulted from the ISR. NRU's IIP is a 10 year plan that addresses the gaps identified in the ISR between modern codes and standards in a prioritized approach. AECL is currently in year 3 of the IIP execution, is on or ahead of schedule to complete the identified improvements. The IIP in conjunction with a License Condition Handbook has replaced the licensing protocol with the Canadian Nuclear Safety Commission, (CNSC). Execution of the IIP to plan supports the continued safe operation of NRU. The ISR was carried out with the recognition that the NRU reactor is a research and isotope producing reactor approaching license renewal and not a power reactor undergoing refurbishment and life extension. Therefore, the IIP is being executed while NRU continues to deliver on its three missions: production of medical isotopes, support for fuels and materials research, and serving as a high flux neutron source in support of research relying on neutron scattering. The IIP is grouped into 5 Global Issue Groups, (GIGs) to support focused execution. The activities and tasks within the five GIGs are being executed via a matrix organization through the use of the Chalk River Laboratories Corrective Action Program to ensure the assignment of actions, completion and evidence to support closure is documented and retained. This paper discusses the approach taken by AECL to license and ensure safe, reliable operation of NRU until 2021 and beyond. (author)

  20. The safety features of an integrated maritime reactor

    International Nuclear Information System (INIS)

    Miyakoshi, Junichi; Yamada, Nobuyuki; Kuwahara, Shin-ichi

    1975-01-01

    The EFDR-80, a typical integrated maritime reactor, which is being developed in West Germany is outlined. The safety features of the integrated maritime reactor are presented with the analysis of reactor accidents and hazards, and are compared with those of the separated maritime reactor. Furthermore, the safety criteria of maritime reactors in Japan and West Germany are compared, and some of the differences are presented from the viewpoint of reactor design and safety analysis. In this report the authors express an earnest desire that the definite and reasonable safety criteria of the integrated maritime reactor should be established and that the safety criteria of the nuclear ship should be standardized internationally. (auth.)

  1. Development of safety analysis technology for integral reactor

    Energy Technology Data Exchange (ETDEWEB)

    Sim, Suk K.; Song, J. H.; Chung, Y. J. and others

    1999-03-01

    Inherent safety features and safety system characteristics of the SMART integral reactor are investigated in this study. Performance and safety of the SMART conceptual design have been evaluated and confirmed through the performance and safety analyses using safety analysis system codes as well as a preliminary performance and safety analysis methodology. SMART design base events and their acceptance criteria are identified to develop a preliminary PIRT for the SMART integral reactor. Using the preliminary PIRT, a set of experimental program for the thermal hydraulic separate effect tests and the integral effect tests was developed for the thermal hydraulic model development and the system code validation. Safety characteristics as well as the safety issues of the integral reactor has been identified during the study, which will be used to resolve the safety issues and guide the regulatory criteria for the integral reactor. The results of the performance and safety analyses performed during the study were used to feedback for the SMART conceptual design. The performance and safety analysis code systems as well as the preliminary safety analysis methodology developed in this study will be validated as the SMART design evolves. The performance and safety analysis technology developed during the study will be utilized for the SMART basic design development. (author)

  2. An Integrated Safety Assessment Methodology for Generation IV Nuclear Systems

    International Nuclear Information System (INIS)

    Leahy, Timothy J.

    2010-01-01

    The Generation IV International Forum (GIF) Risk and Safety Working Group (RSWG) was created to develop an effective approach for the safety of Generation IV advanced nuclear energy systems. Early work of the RSWG focused on defining a safety philosophy founded on lessons learned from current and prior generations of nuclear technologies, and on identifying technology characteristics that may help achieve Generation IV safety goals. More recent RSWG work has focused on the definition of an integrated safety assessment methodology for evaluating the safety of Generation IV systems. The methodology, tentatively called ISAM, is an integrated 'toolkit' consisting of analytical techniques that are available and matched to appropriate stages of Generation IV system concept development. The integrated methodology is intended to yield safety-related insights that help actively drive the evolving design throughout the technology development cycle, potentially resulting in enhanced safety, reduced costs, and shortened development time.

  3. Safety Concepts in Structural Glass Engineering : Towards an Integrated Approach

    NARCIS (Netherlands)

    Bos, F.P.

    2009-01-01

    This dissertation proposes the Integrated Approach to Structural Glass Safety, based on four clearly defined element safety properties, damage sensitivity, relative resistance, redundancy, and fracture mode. The Element Safety Diagram (ESD) is introduced to provide an easy-to-read graphical

  4. Integrating Occupational Health and Safety into TAFE Courses: Curriculum Topics.

    Science.gov (United States)

    Hall, Bob; Mageean, Pauline

    This guide is designed to help technical and further education (TAFE) curriculum writers in Australia integrate safety education into vocational education courses. It provides a general overview of occupational health and safety from the perspective of TAFE trade training and a brief summary of the major health and safety issues that might be…

  5. Food Safety: an Integral Part of Food Security

    International Nuclear Information System (INIS)

    Kilian, Lizette

    2012-01-01

    In recent years, many countries have developed integrated and harmonized food safety and quality control guidelines in accordance with national legislation and international standards to protect the health of consumers. But food safety standards alone are not enough. Radiation technology can complement and supplement existing technologies to ensure food security, safety and quality.

  6. 49 CFR 1106.4 - The Safety Integration Plan process.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 8 2010-10-01 2010-10-01 false The Safety Integration Plan process. 1106.4 Section 1106.4 Transportation Other Regulations Relating to Transportation (Continued) SURFACE... CONSIDERATION OF SAFETY INTEGRATION PLANS IN CASES INVOLVING RAILROAD CONSOLIDATIONS, MERGERS, AND ACQUISITIONS...

  7. Integrated program of using of Probabilistic Safety Analysis in Spain

    International Nuclear Information System (INIS)

    1998-01-01

    Since 25 June 1986, when the CSN (Nuclear Safety Conseil) approve the Integrated Program of Probabilistic Safety Analysis, this program has articulated the main activities of CSN. This document summarize the activities developed during these years and reviews the Integrated programme

  8. Supporting Fernald Site Closure with Integrated Health and Safety Plans as Documented Safety Analyses

    International Nuclear Information System (INIS)

    Kohler, S.; Brown, T.; Fisk, P.; Krach, F.; Klein, B.

    2004-01-01

    At the Fernald Closure Project (FCP) near Cincinnati, Ohio, environmental restoration activities are supported by Documented Safety Analyses (DSAs) that combine the required project-specific Health and Safety Plans, Safety Basis Requirements (SBRs), and Process Requirements (PRs) into single Integrated Health and Safety Plans (I-HASPs). These integrated DSAs employ Integrated Safety Management methodology in support of simplified restoration and remediation activities that, so far, have resulted in the decontamination and demolition (D and D) of over 200 structures, including eight major nuclear production plants. There is one of twelve nuclear facilities still remaining (Silos containing uranium ore residues) with its own safety basis documentation. This paper presents the status of the FCP's safety basis documentation program, illustrating that all of the former nuclear facilities and activities have now replaced. Basis of Interim Operations (BIOs) with I-HASPs as their safety basis during the closure process

  9. Tree Simulation Techniques for Integrated Safety Assessment

    International Nuclear Information System (INIS)

    Melendez Asensio, E.; Izquierdo Rocha, J.M.; Sanchez Perez, M.; Hortal Reymundo, J.; Perez Mulas, A.

    1999-01-01

    techniques are: (a) An unifying theory that should (i) establish the relationship among different approaches and, in particular, be able to demonstrate the standard safety assessment approach as a particular case, (ii) identify implicit assumptions in present practice and (iii) establish a sound scientific reference for an ideal treatment in order to judge the relative importance of implicit and explicit assumptions. In addition, the theoretical developments help to identify the type of applications where the new developments will be a necessary requirement. (b) The capability for simulation of trees. By this we mean the techniques required to be able to efficiently simulate all branches. Historically algorithms able to do this were already implemented in earlier pioneering work for discrete number of branches while stochastic branching requires Montecarlo techniques. (c) The capability to incorporate new types of branching, particularly operator actions. This paper shortly reviews these aspects and justifies in that frame our particular development, denoted here as Integrated Safety Assessment methodology. In this method, the dynamics of the event is followed by transient simulation in tree form, building a Setpoint or Deterministic Dynamic Event Tree (DDET). When a setpoint that should trigger the actuation of a protection is crossed, the tree is opened in branches corresponding to different functioning states of the protection device and each branch followed by the engineering simulator. One of these states is the nominal state, which, in the PSAs, is Associated to the success criterion of the system

  10. Making safety an integral part of 5S in healthcare.

    Science.gov (United States)

    Ikuma, Laura H; Nahmens, Isabelina

    2014-01-01

    Healthcare faces major challenges with provider safety and rising costs, and many organizations are using Lean to instigate change. One Lean tool, 5S, is becoming popular for improving efficiency of physical work environments, and it can also improve safety. This paper demonstrates that safety is an integral part of 5S by examining five specific 5S events in acute care facilities. We provide two arguments for how safety is linked to 5S:1. Safety is affected by 5S events, regardless of whether safety is a specific goal and 2. Safety can and should permeate all five S's as part of a comprehensive plan for system improvement. Reports of 5S events from five departments in one health system were used to evaluate how changes made at each step of the 5S impacted safety. Safety was affected positively in each step of the 5S through initial safety goals and side effects of other changes. The case studies show that 5S can be a mechanism for improving safety. Practitioners may reap additional safety benefits by incorporating safety into 5S events through a safety analysis before the 5S, safety goals and considerations during the 5S, and follow-up safety analysis.

  11. Nuclear safety culture and integrated risk management

    International Nuclear Information System (INIS)

    Joksimovich, V.; Orvis, D.D.

    1993-01-01

    A primary focus of nuclear safety is the prevention of large releases of radioactivity in the case of low-probability severe accidents. An analysis of the anatomy of nuclear (Chernobyl, Three Mile Island Unit 2) and nonnuclear (Challenger, Bhopal, Piper Alpha, etc.) severe accidents yields four broad categories of root causes: human (operating crew response), machine (design with its basic flaws), media (natural phenomena, operational considerations, political environment, commercial pressures, etc.)-providing triggering events, and management (basic organizational safety culture flaws). A strong management can minimize the contributions of humans, machines, and media to the risk arising from the operation of hazardous facilities. One way that management can have a powerful positive influence is through the establishment of a proper safety culture. The term safety culture is used as defined by the International Atomic Energy Agency's International Safety Advisory Group

  12. Safety design integrated in the building delivery system

    DEFF Research Database (Denmark)

    Jørgensen, Kirsten

    2013-01-01

    . The purpose of this article is to demonstrate how safety and health can be integrated in the design phases integrated in the management delivery systems within construction, The method for the research was to go through the building delivery system step by step and create a normative description of what, when......In construction, it is important to view safety and health as an integrated part of the way that “designers” are working. The designers cowers architects, constructors, engineers and others who carry out their consulting services in the design phase of a construction project. The philosophy...... and how to fully integrate safety in each part of the process. The result is a concept and guideline including control forms for how to integrate safety design in the Building Delivery System plus what to do and when. The concept has been tested in an educational context. The practical value...

  13. Determination of Safety Performance Grade of NPP Using Integrated Safety Performance Assessment (ISPA) Program

    International Nuclear Information System (INIS)

    Chung, Dae Wook

    2011-01-01

    Since the beginning of 2000, the safety regulation of nuclear power plant (NPP) has been challenged to be conducted more reasonable, effective and efficient way using risk and performance information. In the United States, USNRC established Reactor Oversight Process (ROP) in 2000 for improving the effectiveness of safety regulation of operating NPPs. The main idea of ROP is to classify the NPPs into 5 categories based on the results of safety performance assessment and to conduct graded regulatory programs according to categorization, which might be interpreted as 'Graded Regulation'. However, the classification of safety performance categories is highly comprehensive and sensitive process so that safety performance assessment program should be prepared in integrated, objective and quantitative manner. Furthermore, the results of assessment should characterize and categorize the actual level of safety performance of specific NPP, integrating all the substantial elements for assessing the safety performance. In consideration of particular regulatory environment in Korea, the integrated safety performance assessment (ISPA) program is being under development for the use in the determination of safety performance grade (SPG) of a NPP. The ISPA program consists of 6 individual assessment programs (4 quantitative and 2 qualitative) which cover the overall safety performance of NPP. Some of the assessment programs which are already implemented are used directly or modified for incorporating risk aspects. The others which are not existing regulatory programs are newly developed. Eventually, all the assessment results from individual assessment programs are produced and integrated to determine the safety performance grade of a specific NPP

  14. Simplifying documentation while approaching site closure: integrated health and safety plans as documented safety analysis

    International Nuclear Information System (INIS)

    Brown, Tulanda

    2003-01-01

    At the Fernald Closure Project (FCP) near Cincinnati, Ohio, environmental restoration activities are supported by Documented Safety Analyses (DSAs) that combine the required project-specific Health and Safety Plans, Safety Basis Requirements (SBRs), and Process Requirements (PRs) into single Integrated Health and Safety Plans (I-HASPs). By isolating any remediation activities that deal with Enriched Restricted Materials, the SBRs and PRs assure that the hazard categories of former nuclear facilities undergoing remediation remain less than Nuclear. These integrated DSAs employ Integrated Safety Management methodology in support of simplified restoration and remediation activities that, so far, have resulted in the decontamination and demolition (D and D) of over 150 structures, including six major nuclear production plants. This paper presents the FCP method for maintaining safety basis documentation, using the D and D I-HASP as an example

  15. Software for the occupational health and safety integrated management system

    International Nuclear Information System (INIS)

    Vătăsescu, Mihaela

    2015-01-01

    This paper intends to present the design and the production of a software for the Occupational Health and Safety Integrated Management System with the view to a rapid drawing up of the system documents in the field of occupational health and safety

  16. Software for the occupational health and safety integrated management system

    Energy Technology Data Exchange (ETDEWEB)

    Vătăsescu, Mihaela [University Politehnica Timisoara, Department of Engineering and Management, 5 Revolutiei street, 331128 Hunedoara (Romania)

    2015-03-10

    This paper intends to present the design and the production of a software for the Occupational Health and Safety Integrated Management System with the view to a rapid drawing up of the system documents in the field of occupational health and safety.

  17. Patient Safety and Workplace Bullying: An Integrative Review.

    Science.gov (United States)

    Houck, Noreen M; Colbert, Alison M

    Workplace bullying is strongly associated with negative nursing outcomes, such as work dissatisfaction, turnover, and intent to leave; however, results of studies examining associations with specific patient safety outcomes are limited or nonspecific. This integrative review explores and synthesizes the published articles that address the impact of workplace nurse bullying on patient safety.

  18. An integrated approach to bicycle safety.

    NARCIS (Netherlands)

    Wittink, R.D.

    1997-01-01

    The advantages of cycling are outlined, as well as the conditions under which use of the bicycle and the safety of cycling can he promoted. Bicycles are an attractive product. The potential to use a bicycle for trips shorter than 5 km is high and it's use can also be substantial for longer

  19. Development of Safety Analysis Technology for Integral Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Sim, S. K. [Korea Atomic Energy Research Institute, Taejeon (Korea); Seul, K. W.; Kim, W. S.; Kim, W. K.; Yun, Y. G.; Ahn, H. J.; Lee, J. S.; Sin, A. D. [Korea Institute of Nuclear Safety, Taejeon (Korea)

    2000-03-01

    The Nuclear Desalination Plant(NDP) is being developed to produce electricity and fresh water, and is expected to locate near population zone. In the aspect of safety, it is required to protect the public and environment from the possible releases of fission products and to prevent the fresh water from the contamination of radioactivity. Thus, in a present study, the safety characteristics of the integral reactor adopting passive and inherent safety features significantly different from existing nuclear power plants were investigated based on the design of foreign and domestic integral reactors. Also, safety requirements applicable to the NDP were analyzed based on the regulatory requirements for current and advanced reactor designs, and use requirements for small-medium size reactors. Based on these analyses, some safety concerns to be considered in the design stage have been identified. They includes the use of proven technology for new safety systems, the systematic classification and selection of design basis accidents, and the safety assurance of desalination-related systems. These efforts to identify and resolve the safety concerns in the design stage will provide the early confidence of SMART safety to designers, and the technical basis to evaluate the safety to reviewers in the future. 8 refs., 20 figs., 4 tabs. (Author)

  20. SBO simulations for Integrated Passive Safety System (IPSS) using MARS

    International Nuclear Information System (INIS)

    Kim, Sang Ho; Jeong, Sung Yeop; Chang, Soon Heung

    2012-01-01

    The current nuclear power plants have lots of active safety systems with some passive safety systems. The safety of current and future nuclear power plants can be enhanced by the application of additional passive safety systems for the ultimate safety. It is helpful to install the passive safety systems on current nuclear power plants without the design change for the licensibility. For solving the problem about the system complexity shown in the Fukushima accidents, the current nuclear power plants are needed to be enhanced by an additional integrated and simplified system. As a previous research, the integrated passive safety system (IPSS) was proposed to solve the safety issues related with the decay heat removal, containment integrity and radiation release. It could be operated by natural phenomena like gravity, natural circulation and pressure difference without AC power. The five main functions of IPSS are: (a) Passive decay heat removal, (b) Passive emergency core cooling, (c) Passive containment cooling, (d) Passive in vessel retention and ex-vessel cooling, and (e) Filtered venting and pressure control. The purpose of this research is to analyze the performances of each function by using MARS code. The simulated accident scenarios were station black out (SBO) and the additional accidents accompanied by SBO

  1. Integrating Occupational Safety and Health into TAFE Courses: Policy Guidelines.

    Science.gov (United States)

    Hill, Graham L.; Mageean, Pauline

    Intended to help administrators, curriculum developers, and teachers integrate occupational health and safety into Australian vocational courses on bricklaying, metal fabrication, and horticulture, this document suggests specific policies and provides further amplification concerning three general policies for that integration. The three general…

  2. Safety climate and culture: Integrating psychological and systems perspectives.

    Science.gov (United States)

    Casey, Tristan; Griffin, Mark A; Flatau Harrison, Huw; Neal, Andrew

    2017-07-01

    Safety climate research has reached a mature stage of development, with a number of meta-analyses demonstrating the link between safety climate and safety outcomes. More recently, there has been interest from systems theorists in integrating the concept of safety culture and to a lesser extent, safety climate into systems-based models of organizational safety. Such models represent a theoretical and practical development of the safety climate concept by positioning climate as part of a dynamic work system in which perceptions of safety act to constrain and shape employee behavior. We propose safety climate and safety culture constitute part of the enabling capitals through which organizations build safety capability. We discuss how organizations can deploy different configurations of enabling capital to exert control over work systems and maintain safe and productive performance. We outline 4 key strategies through which organizations to reconcile the system control problems of promotion versus prevention, and stability versus flexibility. (PsycINFO Database Record (c) 2017 APA, all rights reserved).

  3. The practical implementation of integrated safety management for nuclear safety analysis and fire hazards analysis documentation

    International Nuclear Information System (INIS)

    COLLOPY, M.T.

    1999-01-01

    In 1995 Mr. Joseph DiNunno of the Defense Nuclear Facilities Safety Board issued an approach to describe the concept of an integrated safety management program which incorporates hazard and safety analysis to address a multitude of hazards affecting the public, worker, property, and the environment. Since then the U S . Department of Energy (DOE) has adopted a policy to systematically integrate safety into management and work practices at all levels so that missions can be completed while protecting the public, worker, and the environment. While the DOE and its contractors possessed a variety of processes for analyzing fire hazards at a facility, activity, and job; the outcome and assumptions of these processes have not always been consistent for similar types of hazards within the safety analysis and the fire hazard analysis. Although the safety analysis and the fire hazard analysis are driven by different DOE Orders and requirements, these analyses should not be entirely independent and their preparation should be integrated to ensure consistency of assumptions, consequences, design considerations, and other controls. Under the DOE policy to implement an integrated safety management system, identification of hazards must be evaluated and agreed upon to ensure that the public. the workers. and the environment are protected from adverse consequences. The DOE program and contractor management need a uniform, up-to-date reference with which to plan. budget, and manage nuclear programs. It is crucial that DOE understand the hazards and risks necessarily to authorize the work needed to be performed. If integrated safety management is not incorporated into the preparation of the safety analysis and the fire hazard analysis, inconsistencies between assumptions, consequences, design considerations, and controls may occur that affect safety. Furthermore, confusion created by inconsistencies may occur in the DOE process to grant authorization of the work. In accordance with

  4. The role of risk assessment and safety analysis in integrated safety assessments

    International Nuclear Information System (INIS)

    Niall, R.; Hunt, M.; Wierman, T.E.

    1990-01-01

    To ensure that the design and operation of both nuclear and non- nuclear hazardous facilities is acceptable, and meets all societal safety expectations, a rigorous deterministic and probabilistic assessment is necessary. An approach is introduced, founded on the concept of an ''Integrated Safety Assessment.'' It merges the commonly performed safety and risk analyses and uses them in concert to provide decision makers with the necessary depth of understanding to achieve ''adequacy.'' 3 refs., 1 fig

  5. Safety culture' is integrating 'human' into risk assessment

    International Nuclear Information System (INIS)

    Sugimoto, Taiji

    2014-01-01

    Significance of Fukushima nuclear power accident requested reconsideration of safety standards, of which we had usually no doubt. Risk assessment standard (JIS B 9702), Which was used for repetition of database preparation and cumulative assessment, defined allowable risk and residual risk. However, work site and immediate assessment was indispensable beside such assessment so as to ensure safety. Risk of casualties was absolutely not acceptable in principle and judgments to approve allowable risk needed accountability, which was reminded by safety culture proposed by IAEA and also identified by investigation of organizational cause of Columbia accident. Actor of safety culture would be organization and individual, and mainly individual. Realization of safety culture was conducted by personnel having moral consciousness and firm sense of mission in the course of jobs and working daily with sweat pouring. Safety engineering/technology should have framework integrating human as such totality. (T. Tanaka)

  6. Structural integrity aspects of reactor safety

    Indian Academy of Sciences (India)

    A large experimental programme supported the structural integrity demonstration. ... Categories in which the structures, systems and components (SSC) are .... One of the ways in which the decision to live with the defect can be aided is the .... The Advanced Heavy Water Reactor (AHWR) (figure 18) being designed by BARC ...

  7. Safety Analysis for Medium/Small Size Integral Reactor: Evaluation of Safety Characteristics for Small and Medium Integral Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hho jung; Seul, K W; Ahn, S K; Bang, Y S; Park, D G; Kim, B K; Kim, W S; Lee, J H; Kim, W K; Shim, T M; Choi, H S; Ahn, H J; Jung, D W; Kim, G I; Park, Y M; Lee, Y J [Korea Inst. of Nuclear Safety, Taejon (Korea, Republic of)

    1997-07-01

    The Small and medium integral reactor is developed to be utilized for non-electric areas such as district heating and steam production for desalination and other industrial purposes, and then these applications may typically imply a closeness between the reactor and the user. It requires the reactor to be designed with the adoption of special functional and inherent safety features to ensure and promote a high level of safety and reliability, in comparison with the existing nuclear power plants. The objective of the present study is to establish the bases for the development of regulatory requirements and technical guides to address the special safety characteristics of the small and medium integral reactor. In addition, the study aims to identify and to propose resolutions to the possible safety concerns in the design of the small and medium integral reactor. 34 refs., 20 tabs. (author)

  8. Integration of radiation and physical safety in large radiator facilities

    International Nuclear Information System (INIS)

    Lima, P.P.M.; Benedito, A.M.; Lima, C.M.A.; Silva, F.C.A. da

    2017-01-01

    Growing international concern about radioactive sources after the Sept. 11, 2001 event has led to a strengthening of physical safety. There is evidence that the illicit use of radioactive sources is a real possibility and may result in harmful radiological consequences for the population and the environment. In Brazil there are about 2000 medical, industrial and research facilities with radioactive sources, of which 400 are Category 1 and 2 classified by the - International Atomic Energy Agency - AIEA, where large irradiators occupy a prominent position due to the very high cobalt-60 activities. The radiological safety is well established in these facilities, due to the intense work of the authorities in the Country. In the paper the main aspects on radiological and physical safety applied in the large radiators are presented, in order to integrate both concepts for the benefit of the safety as a whole. The research showed that the items related to radiation safety are well defined, for example, the tests on the access control devices to the irradiation room. On the other hand, items related to physical security, such as effective control of access to the company, use of safety cameras throughout the company, are not yet fully incorporated. Integration of radiation and physical safety is fundamental for total safety. The elaboration of a Brazilian regulation on the subject is of extreme importance

  9. Patient safety and infection control: bases for curricular integration.

    Science.gov (United States)

    Silva, Andréa Mara Bernardes da; Bim, Lucas Lazarini; Bim, Felipe Lazarini; Sousa, Alvaro Francisco Lopes; Domingues, Pedro Castania Amadio; Nicolussi, Adriana Cristina; Andrade, Denise de

    2018-05-01

    To analyze curricular integration between teaching of patient safety and good infection prevention and control practices. Integrative review, designed to answer the question: "How does curricular integration of content about 'patient safety teaching' and content about 'infection prevention and control practices' occur in undergraduate courses in the health field?". The following databases were searched for primary studies: CINAHL, LILACS, ScienceDirect, Web of Science, Scopus, Europe PMC and MEDLINE. The final sample consisted of 13 studies. After content analysis, primary studies were grouped into two subject categories: "Innovative teaching practices" and "Curricular evaluation. Patient safety related to infection prevention and control practices is present in the curriculum of health undergraduate courses, but is not coordinated with other themes, is taught sporadically, and focuses mainly on hand hygiene.

  10. The development of integrated safety assessment technology

    International Nuclear Information System (INIS)

    Yoo, Keon Joong; Park, Chang Kyu; Kim, Tae Un; Han, Sang Hoon; Yang, Joon Eon; Lim, Tae Jin; Han, Jae Joo; Je, Moo Seong; An, Kwang Il; Kim, Shi Dal; Jeong, Jong Tae; Jeong, Kwang Seop; Jin, Yeong Ho; Kim, Dong Ha; Kim, Kil Yoo; Cho, Yeong Kyoon; Jeong, Won Dae; Jang, Seung Cheol; Choi, Yeong; Park, Soo Yong; Seong, Tae Yong; Song, Yong Man; Kang, Dae Il; Park, Jin Hee; Jang, Seon Joo; Hwang, Mi Jeong; Choi, Seon Yeong

    1993-05-01

    For the purpose of developing the integrated PSA methodology and computer codes, Level-1 and Level-2 PSA methodology and tools were reviewed and improved. The Level-1 PSA computer code package KIRAP was improved and released by the name of KIRAP Release 2.0 Several Human reliability analysis and common cause failure analysis methods was reviewed and compared. For the development of Level-2 PSA computer code, several level-1 and Level-2 interface methods and containment event tree development methods were reviewed and compared. And the new technology such as artificial intelligence was reviewed if the technology can be applied to the development of PSA methodology.(Author)

  11. 77 FR 34123 - Pipeline Safety: Public Meeting on Integrity Management of Gas Distribution Pipelines

    Science.gov (United States)

    2012-06-08

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2012-0100] Pipeline Safety: Public Meeting on Integrity Management of Gas Distribution Pipelines AGENCY: Office of Pipeline Safety, Pipeline and Hazardous Materials Safety Administration, DOT. ACTION...

  12. Development of safety analysis technology for integral reactor

    International Nuclear Information System (INIS)

    Kim, Hee Cheol; Kim, K. K.; Kim, S. H.

    2002-04-01

    The state-of-the-arts for the integral reactor was performed to investigate the safety features. The safety and performance of SMART were assessed using the technologies developed during the study. For this purpose, the computer code system and the analysis methodology were developed and the safety and performance analyses on SMART basic design were carried out for the design basis event and accident. The experimental facilities were designed for the core flow distribution test and the self-pressurizing pressurizer performance test. The tests on the 2-phase critical flow with non-condensable gas were completed and the results were used to assess the critical flow model. Probabilistic Safety Assessment(PSA) was carried out to evaluate the safety level and to optimize the design by identifying and remedying any weakness in the design. A joint study with KINS was carried out to promote licensing environment. The generic safety issues of integral reactors were identified and the solutions were formulated. The economic evaluation of the SMART desalination plant and the activities related to the process control were carried out in the scope of the study

  13. 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

  14. 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...

  15. Safety on a Rural Community College Campus via Integrated Communications

    Science.gov (United States)

    Gnage, Marie Foster; Dziagwa, Connie; White, Dave

    2009-01-01

    West Virginia University at Parkersburg uses a two-way emergency system as a baseline for emergency communications. The college has found that such a system, a key component of its safety and crisis management plan, can be integrated with other communication initiatives to provide focused security on the campus.

  16. Integrated safety case development for deep geological repositories

    International Nuclear Information System (INIS)

    Kawamura, Hideki; McKinley, Ian G.

    2008-01-01

    The paper will illustrate an 'integrated safety case', which involves combining both pre-closure and post-closure safety arguments from the point of view of a repository implementer, who must also ensure that projects are practical, acceptable and economic. The post-closure safety case is based on the performance of a number of barriers, which are established during construction, operation and closure. Such barriers must be confirmed using quality assured methods, supported, as required, by inspection and monitoring. The requirement for integrated assessment means that even the final process to end institutional control and transfer any liabilities from the implementer needs to be considered at present, even though this will undoubtedly be refined and tailored to the site characteristics over the many decades that will pass before this occurs. To illustrate the practical application of this approach, assessment of variants for remote-handled emplacement of the EBS for disposal of HLW in Japan will be discussed. (author)

  17. Safety design integrated in the Building Delivery System

    DEFF Research Database (Denmark)

    Jørgensen, Kirsten

    2012-01-01

    phases of the building delivery system by using the principle of the lean construction modelling. The method for the research was to go through the lean construction building delivery system step by step and create a normative description of what to do, when to do and how to do to fully integration...... of safety in each process. The group of participants who created the description had a high experience in a combination of research, safety and health in general and especial in construction and knowledge of the lean construction processes both from the clients perspective as well as from the designers...... and the consultants. The result is a concept and guideline including control schemes for how to integrate safety design in the lean construction building delivery system including what to do and when. The concept has been tested in an educational context and found useful by the designers. The practical value...

  18. Integrating Safeguards and Security with Safety into Design

    International Nuclear Information System (INIS)

    Bean, Robert S.; Hockert, John W.; Hebditch, David J.

    2009-01-01

    There is a need to minimize security risks, proliferation hazards, and safety risks in the design of new nuclear facilities in a global environment of nuclear power expansion, while improving the synergy of major design features and raising operational efficiency. In 2008, the U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA) launched the Next Generation Safeguards Initiative (NGSI) covering many safeguards areas. One of these, launched by NNSA with support of the DOE Office of Nuclear Energy, was a multi-laboratory project, led by the Idaho National Laboratory (INL), to develop safeguards by design. The proposed Safeguards-by-Design (SBD) process has been developed as a structured approach to ensure the timely, efficient, and cost effective integration of international safeguards and other nonproliferation barriers with national material control and accountability, physical security, and safety objectives into the overall design process for the nuclear facility lifecycle. A graded, iterative process was developed to integrate these areas throughout the project phases. It identified activities, deliverables, interfaces, and hold points covering both domestic regulatory requirements and international safeguards using the DOE regulatory environment as exemplar to provide a framework and guidance for project management and integration of safety with security during design. Further work, reported in this paper, created a generalized SBD process which could also be employed within the licensed nuclear industry and internationally for design of new facilities. Several tools for integrating safeguards, safety, and security into design are discussed here. SBD appears complementary to the EFCOG TROSSI process for security and safety integration created in 2006, which focuses on standardized upgrades to enable existing DOE facilities to meet a more severe design basis threat. A collaborative approach is suggested.

  19. Integrated Approaches to Occupational Health and Safety: A Systematic Review.

    Science.gov (United States)

    Cooklin, A; Joss, N; Husser, E; Oldenburg, B

    2017-09-01

    The study objective was to conduct a systematic review of the effectiveness of integrated workplace interventions that combine health promotion with occupational health and safety. Electronic databases (n = 8), including PsychInfo and MEDLINE, were systematically searched. Studies included were those that reported on workplace interventions that met the consensus definition of an "integrated approach," published in English, in the scientific literature since 1990. Data extracted were occupation, worksite, country, sample size, intervention targets, follow-up period, and results reported. Quality was assessed according to American College of Occupational and Environmental Medicine Practice Guidelines. Heterogeneity precluded formal meta-analyses. Results were classified according to the outcome(s) assessed into five categories (health promotion, injury prevention, occupational health and safety management, psychosocial, and return-on-investment). Narrative synthesis of outcomes was performed. A total of 31 eligible studies were identified; 23 (74%) were (quasi-)experimental trials. Effective interventions were most of those aimed at improving employee physical or mental health. Less consistent results were reported from integrated interventions targeting occupational health and safety management, injury prevention, or organizational cost savings. Integrated approaches have been posed as comprehensive solutions to complex issues. Empirical evidence, while still emerging, provides some support for this. Continuing investment in, and evaluation of, integrated approaches are worthwhile.

  20. 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.

  1. Integrating environment health and safety management at Petro-Canada

    International Nuclear Information System (INIS)

    Raymond, G.

    1993-01-01

    Petro-Canada has developed a tool to integrate, measure, and improve its management systems of environment, health, and safety (EH ampersand S). This tool, called the Total Loss Management System, is described in the areas of general management issues, policies and procedures, evaluations, organization, stewardship, issue management, and performance measures. Petro-Canada's policies on occupational health and safety are consistent with its environmental policy, being structured in the same way. An integrated audit system is used to cover health, safety, industrial hygiene, reliability, environment, and risk management. EH ampersand S matters are integrated at the corporate level in a separate department. Regional divisions review EH ampersand S performance every month, incidents are discussed, and preventive measures are taken as necessary. Regional performances are combined every quarter for ultimate presentation to the Petro-Canada board. New or emerging issues that may affect divisions are assigned an issue sponsor, a member of divisional management who makes sure the issue receives the resources necessary to study and define its impact. Examples of issues include soil contamination, process hazard management, and benzene exposure limits. Performance measures flow from the corporate environment and occupational health and safety policies, and come in two types: those that measure activities to improve performance and those that measure the outcome of the activities

  2. A simple reliability block diagram method for safety integrity verification

    International Nuclear Information System (INIS)

    Guo Haitao; Yang Xianhui

    2007-01-01

    IEC 61508 requires safety integrity verification for safety related systems to be a necessary procedure in safety life cycle. PFD avg must be calculated to verify the safety integrity level (SIL). Since IEC 61508-6 does not give detailed explanations of the definitions and PFD avg calculations for its examples, it is difficult for common reliability or safety engineers to understand when they use the standard as guidance in practice. A method using reliability block diagram is investigated in this study in order to provide a clear and feasible way of PFD avg calculation and help those who take IEC 61508-6 as their guidance. The method finds mean down times (MDTs) of both channel and voted group first and then PFD avg . The calculated results of various voted groups are compared with those in IEC61508 part 6 and Ref. [Zhang T, Long W, Sato Y. Availability of systems with self-diagnostic components-applying Markov model to IEC 61508-6. Reliab Eng System Saf 2003;80(2):133-41]. An interesting outcome can be realized from the comparison. Furthermore, although differences in MDT of voted groups exist between IEC 61508-6 and this paper, PFD avg of voted groups are comparatively close. With detailed description, the method of RBD presented can be applied to the quantitative SIL verification, showing a similarity of the method in IEC 61508-6

  3. Safety studies on Korean fusion DEMO plant using integrated safety assessment methodology

    International Nuclear Information System (INIS)

    Oh, Kyemin; Kang, Myoung-suk; Heo, Gyunyoung; Kim, Hyoung-chan

    2014-01-01

    Highlights: •The purpose of this paper is to suggest methodology that can investigate safety issues and provides a case study for Korean fusion DEMO plant. •The concepts of integrated safety assessment methodology (ISAM) that can be applied in addressing regulatory requirements and recognizing safety issues for K-DEMO were emphasized. •Phenomena identification and ranking table (PIRT) was proposed. It can recognize vulnerabilities of systems and identify the gaps in technical areas requiring additional researches. •This work is expected to contribute on the conceptual design of safety features for K-DEMO to design engineers and the guidance for regulatory requirements to licensers. -- Abstract: The purpose of this paper is to suggest methodology that can investigate safety issues and provides a case study for Korean fusion DEMO plant (K-DEMO) as a part of R and D program through the National Fusion Research Institute of Korea. Even though nuclear regulation and licensing framework is well setup due to the operating and design experience of Pressurized Water Reactors (PWRs) since 1970s, the regulatory authority of South Korea has concerns on the challenge of facing new nuclear facilities including K-DEMO due to the differences in systems, materials, and inherent safety feature from conventional PWRs. Even though the follow-up of the ITER license process facilitates to deal with significant safety issues of fusion facilities, a licensee as well as a licenser should identify the gaps between ITER and DEMO in terms of safety issues. First we reviewed the methods of conducting safety analysis for unprecedented nuclear facilities such as Generation IV reactors, particularly very high temperature reactor (VHTR), which is called as integrated safety assessment methodology (ISAM). Second, the analysis for the conceptual design of K-DEMO on the basis of ISAM was conducted. The ISAM consists of five analytical tools to develop the safety requirements from licensee

  4. Safety studies on Korean fusion DEMO plant using integrated safety assessment methodology

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Kyemin; Kang, Myoung-suk [Kyung Hee University, Youngin-si, Gyeonggi-do 446-701 (Korea, Republic of); Heo, Gyunyoung, E-mail: gheo@khu.ac.kr [Kyung Hee University, Youngin-si, Gyeonggi-do 446-701 (Korea, Republic of); Kim, Hyoung-chan [National Fusion Research Institute, Daejeon-si 305-333 (Korea, Republic of)

    2014-10-15

    Highlights: •The purpose of this paper is to suggest methodology that can investigate safety issues and provides a case study for Korean fusion DEMO plant. •The concepts of integrated safety assessment methodology (ISAM) that can be applied in addressing regulatory requirements and recognizing safety issues for K-DEMO were emphasized. •Phenomena identification and ranking table (PIRT) was proposed. It can recognize vulnerabilities of systems and identify the gaps in technical areas requiring additional researches. •This work is expected to contribute on the conceptual design of safety features for K-DEMO to design engineers and the guidance for regulatory requirements to licensers. -- Abstract: The purpose of this paper is to suggest methodology that can investigate safety issues and provides a case study for Korean fusion DEMO plant (K-DEMO) as a part of R and D program through the National Fusion Research Institute of Korea. Even though nuclear regulation and licensing framework is well setup due to the operating and design experience of Pressurized Water Reactors (PWRs) since 1970s, the regulatory authority of South Korea has concerns on the challenge of facing new nuclear facilities including K-DEMO due to the differences in systems, materials, and inherent safety feature from conventional PWRs. Even though the follow-up of the ITER license process facilitates to deal with significant safety issues of fusion facilities, a licensee as well as a licenser should identify the gaps between ITER and DEMO in terms of safety issues. First we reviewed the methods of conducting safety analysis for unprecedented nuclear facilities such as Generation IV reactors, particularly very high temperature reactor (VHTR), which is called as integrated safety assessment methodology (ISAM). Second, the analysis for the conceptual design of K-DEMO on the basis of ISAM was conducted. The ISAM consists of five analytical tools to develop the safety requirements from licensee

  5. A dynamic probabilistic safety margin characterization approach in support of Integrated Deterministic and Probabilistic Safety Analysis

    International Nuclear Information System (INIS)

    Di Maio, Francesco; Rai, Ajit; Zio, Enrico

    2016-01-01

    The challenge of Risk-Informed Safety Margin Characterization (RISMC) is to develop a methodology for estimating system safety margins in the presence of stochastic and epistemic uncertainties affecting the system dynamic behavior. This is useful to support decision-making for licensing purposes. In the present work, safety margin uncertainties are handled by Order Statistics (OS) (with both Bracketing and Coverage approaches) to jointly estimate percentiles of the distributions of the safety parameter and of the time required for it to reach these percentiles values during its dynamic evolution. The novelty of the proposed approach consists in the integration of dynamic aspects (i.e., timing of events) into the definition of a dynamic safety margin for a probabilistic Quantification of Margin and Uncertainties (QMU). The system here considered for demonstration purposes is the Lead–Bismuth Eutectic- eXperimental Accelerator Driven System (LBE-XADS). - Highlights: • We integrate dynamic aspects into the definition of a safety margins. • We consider stochastic and epistemic uncertainties affecting the system dynamics. • Uncertainties are handled by Order Statistics (OS). • We estimate the system grace time during accidental scenarios. • We apply the approach to an LBE-XADS accidental scenario.

  6. Engineering systems reliability, safety, and maintenance an integrated approach

    CERN Document Server

    Dhillon, B S

    2017-01-01

    Today, engineering systems are an important element of the world economy and each year billions of dollars are spent to develop, manufacture, operate, and maintain various types of engineering systems around the globe. Many of these systems are highly sophisticated and contain millions of parts. For example, a Boeing jumbo 747 is made up of approximately 4.5 million parts including fasteners. Needless to say, reliability, safety, and maintenance of systems such as this have become more important than ever before.  Global competition and other factors are forcing manufacturers to produce highly reliable, safe, and maintainable engineering products. Therefore, there is a definite need for the reliability, safety, and maintenance professionals to work closely during design and other phases. Engineering Systems Reliability, Safety, and Maintenance: An Integrated Approach eliminates the need to consult many different and diverse sources in the hunt for the information required to design better engineering syste...

  7. Safety characteristics of the integral fast reactor concept

    International Nuclear Information System (INIS)

    Marchaterre, J.F.; Cahalan, J.E.; Sevy, R.H.; Wright, A.E.

    1985-01-01

    The Integral Fast Reactor (IFR) concept is an innovative approach to liquid metal reactor design which is being studied by Argonne National Laboratory. Two of the key features of the IFR design are a metal fuel core design, based on the fuel technology developed at EBR-II, and an integral fuel cycle with a colocated fuel cycle facility based on the compact and simplified process steps made possible by the use of metal fuel. The paper presents the safety characteristics of the IFR concept which derive from the use of metal fuel. Liquid metal reactors, because of the low pressure coolant operating far below its boiling point, the natural circulation capability, and high system heat capacities, possess a high degree of inherent safety. The use of metallic fuel allows the reactor designer to further enhance the system capability for passive accommodation of postulated accidents

  8. The structural integrity safety case for Sizewell B power station

    International Nuclear Information System (INIS)

    Gerachty, J.E.

    1993-01-01

    This paper presents the safety case approach adopted for the components of the Sizewell 'B' Power Station for which a high degree of structural integrity is required. Such components include the Reactor Pressure Vessel, Steam Generator and Pressuriser for which Incredibility of Failure is claimed. The two parts of the case involve achievement and demonstration of integrity. This is achieved by extensive measures involving design, manufacture, materials and inspection. The demonstration has required a fracture mechanics approach. The specific role of inspection validation and its relation to critical defect size is described. (author)

  9. Criticality safety evaluations - a open-quotes stalking horseclose quotes for integrated safety assessment

    International Nuclear Information System (INIS)

    Williams, R.A.

    1995-01-01

    The Columbia Fuel Fabrication Facility of the Westinghouse Commercial Nuclear Fuel Division manufactures low-enriched uranium fuel and associated components for use in commercial pressurized water power reactors. To support development of a comprehensive integrated safety assessment (ISA) for the facility, as well as to address increasing U.S. Nuclear Regulatory Commission (NRC) expectations regarding such a facility's criticality safety assessments, a project is under way to complete criticality safety evaluations (CSEs) of all plant systems used in processing nuclear materials. Each CSE is made up of seven sections, prepared by a multidisciplinary team of process engineers, systems engineers, safety engineers, maintenance representatives, and operators. This paper provides a cursory outline of the type of information presented in a CSE

  10. Criticality safety evaluations - a {open_quotes}stalking horse{close_quotes} for integrated safety assessment

    Energy Technology Data Exchange (ETDEWEB)

    Williams, R.A. [Westinghouse Electric Corp., Columbia, SC (United States)

    1995-12-31

    The Columbia Fuel Fabrication Facility of the Westinghouse Commercial Nuclear Fuel Division manufactures low-enriched uranium fuel and associated components for use in commercial pressurized water power reactors. To support development of a comprehensive integrated safety assessment (ISA) for the facility, as well as to address increasing U.S. Nuclear Regulatory Commission (NRC) expectations regarding such a facility`s criticality safety assessments, a project is under way to complete criticality safety evaluations (CSEs) of all plant systems used in processing nuclear materials. Each CSE is made up of seven sections, prepared by a multidisciplinary team of process engineers, systems engineers, safety engineers, maintenance representatives, and operators. This paper provides a cursory outline of the type of information presented in a CSE.

  11. Integrated safety assessment report, Haddam Neck Plant (Docket No. 50-213): Integrated Safety Assessment Program: Draft report

    International Nuclear Information System (INIS)

    1987-07-01

    The integrated assessment is conducted on a plant-specific basis to evaluate all licensing actions, licensee initiated plant improvements and selected unresolved generic/safety issues to establish implementation schedules for each item. Procedures allow for a periodic updating of the schedules to account for licensing issues that arise in the future. The Haddam Neck Plant is one of two plants being reviewed under the pilot program. This report indicates how 82 topics selected for review were addressed, and presents the staff's recommendations regarding the corrective actions to resolve the 82 topics and other actions to enhance plant safety. 135 refs., 4 figs., 5 tabs

  12. Integral type small PWR with stand-alone safety

    International Nuclear Information System (INIS)

    Makihara, Yoshiaki

    2001-01-01

    A feasibility study is achieved on an integral type small PWR with stand-alone safety. It is designed to have the following features. (1) The coolant does not leak out at any accidental condition. (2) The fuel failure does never occur while it is supposed on the large scale PWR at the design base accident. (3) At any accidental condition the safety is secured without any support from the outside (stand-alone safety secure). (4) It has self-regulating characteristics and easy controllability. The above features can be satisfied by integrate the steam generator and CRDM in the reactor vessel while the pipe line break has to be considered on the conventional PWR. Several counter measures are planned to satisfy the above features. The economy feature is also attained by several simplifications such as (1) elimination of main coolant piping and pressurizer by the integration of primary cooling system and self-pressurizing, (2) elimination of RCP by application of natural circulating system, (3) elimination of ECCS and accumulator by application of static safety system, (4) large scale volume reduction of the container vessel by application of integrated primary cooling system, (5) elimination of boric acid treatment by deletion of chemical shim. The long operation period such as 10 years can be attained by the application of Gd fuel in one batch refueling. The construction period can be shortened by the standardizing the design and the introduction of modular component system. Furthermore the applicability of the reduced modulation core is also considered. (K. Tsuchihashi)

  13. TWRS safety and technical integration risk management plan

    International Nuclear Information System (INIS)

    Fordham, R.A.

    1996-01-01

    The objectives of the Tank Waste Remediation System (TWRS) Safety and Technical Integration (STI) programmatic risk management program are to assess, analyze, and handle risks associated with TWRS STI responsibilities and to communicate information about the actions being taken and the results to enable decision making. The objective of this TWRS STI Risk Management Plan is to communicate a consistent approach to risk management that will be used by the organization

  14. Safety integrity requirements for computer based I ampersand C systems

    International Nuclear Information System (INIS)

    Thuy, N.N.Q.; Ficheux-Vapne, F.

    1997-01-01

    In order to take into account increasingly demanding functional requirements, many instrumentation and control (I ampersand C) systems in nuclear power plants are implemented with computers. In order to ensure the required safety integrity of such equipment, i.e., to ensure that they satisfactorily perform the required safety functions under all stated conditions and within stated periods of time, requirements applicable to these equipment and to their life cycle need to be expressed and followed. On the other hand, the experience of the last years has led EDF (Electricite de France) and its partners to consider three classes of systems and equipment, according to their importance to safety. In the EPR project (European Pressurized water Reactor), these classes are labeled E1A, E1B and E2. The objective of this paper is to present the outline of the work currently done in the framework of the ETC-I (EPR Technical Code for I ampersand C) regarding safety integrity requirements applicable to each of the three classes. 4 refs., 2 figs

  15. Advancing medication infusion safety through the clinical integration of technology.

    Science.gov (United States)

    Gerhart, Donald; O'Shea, Kristen; Muller, Sharon

    2013-01-01

    Adverse drug events resulting from errors in prescribing or administering medications are preventable. Within a hospital system, numerous technologies are employed to address the common sources of medication error, including the use of electronic medical records, physician order entry, smart infusion pumps, and barcode medication administration systems. Infusion safety is inherently risky because of the high-risk medications administered and the lack of integration among the stand-alone systems in most institutions. Intravenous clinical integration (IVCI) is a technology that connects electronic medical records, physician order entry, smart infusion pumps, and barcode medication administration systems. It combines the safety features of an automatically programmed infusion pump (drug, concentration, infusion rate, and patient weight, all auto-programmed into the device) with software that provides visibility to real-time clinical infusion data. Our article describes the characteristics of IVCI at WellSpan Health and its impact on patient safety. The integrated infusion system has the capability of reducing medication errors, improving patient care, reducing in-facility costs, and supporting asset management. It can enhance continuous quality improvement efforts and efficiency of clinical work flow. After implementing IVCI, the institution realized a safer patient environment and a more streamlined work flow for pharmacy and nursing.

  16. Improving occupational safety and health by integration into product development

    DEFF Research Database (Denmark)

    Broberg, Ole

    1996-01-01

    A cross-sectional case study was performed in a large company producing electro-mechanical products for industrial application. The objectives were: (i) to study the product development process and the role of key actors', (ii) to identify current practice on integrating occupational safety and h...... and studies of documents. A questionnaire regarding product development tasks and occupational safety and health were distributed to 30 design and production engineers. A total of 27 completed the questionnaire corresponding to a response rate of 90 per cent.......A cross-sectional case study was performed in a large company producing electro-mechanical products for industrial application. The objectives were: (i) to study the product development process and the role of key actors', (ii) to identify current practice on integrating occupational safety...... and health into the development process, especially the efforts and attitudes of design and production engineers', and (iii) to identify key actors'reflections on how to improve this integration. The study was based on qualitative as well as quantitative methods including interviews, questionnaires...

  17. Design of integrated passive safety system (IPSS) for ultimate passive safety of nuclear power plants

    International Nuclear Information System (INIS)

    Chang, Soon Heung; Kim, Sang Ho; Choi, Jae Young

    2013-01-01

    Highlights: • We newly propose the design concept of integrated passive safety system (IPSS). • It has five safety functions for decay heat removal and severe accident mitigation. • Simulations for IPSS show that core melt does not occur in accidents with SBO. • IPSS can achieve the passive in-vessel retention and ex-vessel cooling strategy. • The applicability of IPSS is high due to the installation outside the containment. -- Abstract: The design concept of integrated passive safety system (IPSS) which can perform various passive safety functions is proposed in this paper. It has the various functions of passive decay heat removal system, passive safety injection system, passive containment cooling system, passive in-vessel retention and cavity flooding system, and filtered venting system with containment pressure control. The objectives of this paper are to propose the conceptual design of an IPSS and to estimate the design characters of the IPSS with accident simulations using MARS code. Some functions of the IPSS are newly proposed and the other functions are reviewed with the integration of the functions. Consequently, all of the functions are modified and integrated for simplicity of the design in preparation for beyond design based accidents (BDBAs) focused on a station black out (SBO). The simulation results with the IPSS show that the decay heat can be sufficiently removed in accidents that occur with a SBO. Also, the molten core can be retained in a vessel via the passive in-vessel retention strategy of the IPSS. The actual application potential of the IPSS is high, as numerous strong design characters are evaluated. The installation of the IPSS into the original design of a nuclear power plant requires minimal design change using the current penetrations of the containment. The functions are integrated in one or two large tanks outside the containment. Furthermore, the operation time of the IPSS can be increased by refilling coolant from the

  18. A Novel Control Algorithm for Integration of Active and Passive Vehicle Safety Systems in Frontal Collisions

    Directory of Open Access Journals (Sweden)

    Daniel Wallner

    2010-10-01

    Full Text Available The present paper investigates an approach to integrate active and passive safety systems of passenger cars. Worldwide, the introduction of Integrated Safety Systems and Advanced Driver Assistance Systems (ADAS is considered to continue the today

  19. A management system integrating radiation protection and safety supporting safety culture in the hospital

    International Nuclear Information System (INIS)

    Almen, A.; Lundh, C.

    2015-01-01

    Quality assurance has been identified as an important part of radiation protection and safety for a considerable time period. A rational expansion and improvement of quality assurance is to integrate radiation protection and safety in a management system. The aim of this study was to explore factors influencing the implementing strategy when introducing a management system including radiation protection and safety in hospitals and to outline benefits of such a system. The main experience from developing a management system is that it is possible to create a vast number of common policies and routines for the whole hospital, resulting in a cost-efficient system. One of the key benefits is the involvement of management at all levels, including the hospital director. Furthermore, a transparent system will involve staff throughout the organisation as well. A management system supports a common view on what should be done, who should do it and how the activities are reviewed. An integrated management system for radiation protection and safety includes key elements supporting a safety culture. (authors)

  20. A plan for safety and integrity of research reactor components

    International Nuclear Information System (INIS)

    Moatty, Mona S. Abdel; Khattab, M.S.

    2013-01-01

    Highlights: ► A plan for in-service inspection of research reactor components is put. ► Section XI of the ASME Code requirements is applied. ► Components subjected to inspection and their classes are defined. ► Flaw evaluation and its acceptance–rejection criteria are reviewed. ► A plan of repair or replacement is prepared. -- Abstract: Safety and integrity of a research reactor that has been operated over 40 years requires frequent and thorough inspection of all the safety-related components of the facility. The need of increasing the safety is the need of improving the reliability of its systems. Diligent and extensive planning of in-service inspection (ISI) of all reactor components has been imposed for satisfying the most stringent safety requirements. The Safeguards Officer's responsibilities of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code ASME Code have been applied. These represent the most extensive and time-consuming part of ISI program, and identify the components subjected to inspection and testing, methods of component classification, inspection and testing techniques, acceptance/rejection criteria, and the responsibilities. The paper focuses on ISI planning requirements for welded systems such as vessels, piping, valve bodies, pump casings, and control rod-housing parts. The weld in integral attachments for piping, pumps, and valves are considered too. These are taken in consideration of safety class (1, 2, 3, etc.), reactor age, and weld type. The parts involve in the frequency of inspection, the examination requirements for each inspection, the examination method are included. Moreover the flaw evaluation, the plan of repair or replacement, and the qualification of nondestructive examination personnel are considered

  1. The mediating role of integration of safety by activity versus operator between organizational culture and safety climate.

    Science.gov (United States)

    Auzoult, Laurent; Gangloff, Bernard

    2018-04-20

    In this study, we analyse the impact of the organizational culture and introduce a new variable, the integration of safety, which relates to the modalities for the implementation and adoption of safety in the work process, either through the activity or by the operator. One hundred and eighty employees replied to a questionnaire measuring the organizational climate, the safety climate and the integration of safety. We expected that implementation centred on the activity or on the operator would mediate the relationship between the organizational culture and the safety climate. The results support our assumptions. A regression analysis highlights the positive impact on the safety climate of organizational values of the 'rule' and 'support' type, as well as of integration by the operator and activity. Moreover, integration mediates the relation between these variables. The results suggest to take into account organizational culture and to introduce different implementation modalities to improve the safety climate.

  2. Large Scale System Safety Integration for Human Rated Space Vehicles

    Science.gov (United States)

    Massie, Michael J.

    2005-12-01

    Since the 1960s man has searched for ways to establish a human presence in space. Unfortunately, the development and operation of human spaceflight vehicles carry significant safety risks that are not always well understood. As a result, the countries with human space programs have felt the pain of loss of lives in the attempt to develop human space travel systems. Integrated System Safety is a process developed through years of experience (since before Apollo and Soyuz) as a way to assess risks involved in space travel and prevent such losses. The intent of Integrated System Safety is to take a look at an entire program and put together all the pieces in such a way that the risks can be identified, understood and dispositioned by program management. This process has many inherent challenges and they need to be explored, understood and addressed.In order to prepare truly integrated analysis safety professionals must gain a level of technical understanding of all of the project's pieces and how they interact. Next, they must find a way to present the analysis so the customer can understand the risks and make decisions about managing them. However, every organization in a large-scale project can have different ideas about what is or is not a hazard, what is or is not an appropriate hazard control, and what is or is not adequate hazard control verification. NASA provides some direction on these topics, but interpretations of those instructions can vary widely.Even more challenging is the fact that every individual/organization involved in a project has different levels of risk tolerance. When the discrete hazard controls of the contracts and agreements cannot be met, additional risk must be accepted. However, when one has left the arena of compliance with the known rules, there can be no longer be specific ground rules on which to base a decision as to what is acceptable and what is not. The integrator must find common grounds between all parties to achieve

  3. Evaluation of Vehicle-Based Crash Severity Metrics.

    Science.gov (United States)

    Tsoi, Ada H; Gabler, Hampton C

    2015-01-01

    Vehicle change in velocity (delta-v) is a widely used crash severity metric used to estimate occupant injury risk. Despite its widespread use, delta-v has several limitations. Of most concern, delta-v is a vehicle-based metric which does not consider the crash pulse or the performance of occupant restraints, e.g. seatbelts and airbags. Such criticisms have prompted the search for alternative impact severity metrics based upon vehicle kinematics. The purpose of this study was to assess the ability of the occupant impact velocity (OIV), acceleration severity index (ASI), vehicle pulse index (VPI), and maximum delta-v (delta-v) to predict serious injury in real world crashes. The study was based on the analysis of event data recorders (EDRs) downloaded from the National Automotive Sampling System / Crashworthiness Data System (NASS-CDS) 2000-2013 cases. All vehicles in the sample were GM passenger cars and light trucks involved in a frontal collision. Rollover crashes were excluded. Vehicles were restricted to single-event crashes that caused an airbag deployment. All EDR data were checked for a successful, completed recording of the event and that the crash pulse was complete. The maximum abbreviated injury scale (MAIS) was used to describe occupant injury outcome. Drivers were categorized into either non-seriously injured group (MAIS2-) or seriously injured group (MAIS3+), based on the severity of any injuries to the thorax, abdomen, and spine. ASI and OIV were calculated according to the Manual for Assessing Safety Hardware. VPI was calculated according to ISO/TR 12353-3, with vehicle-specific parameters determined from U.S. New Car Assessment Program crash tests. Using binary logistic regression, the cumulative probability of injury risk was determined for each metric and assessed for statistical significance, goodness-of-fit, and prediction accuracy. The dataset included 102,744 vehicles. A Wald chi-square test showed each vehicle-based crash severity metric

  4. Need for an "integrated safety assessment" of GMOs, linking food safety and environmental considerations.

    Science.gov (United States)

    Haslberger, Alexander G

    2006-05-03

    information. An integrated assessment might help to focus and save capacities in highly technical areas such as molecular characterization or profiling, which are often necessary for both assessments. In the area of establishing international standards for traded foods, such as for the newly created Standards in Trade and Development Facility (STDF), an integrated assessment might help in the consideration of important environmental aspects involved in health and food safety. Furthermore, an established integrated view on GMOs may create greater consumer confidence in the technology.

  5. Office of River Protection Integrated Safety Management System Description

    Energy Technology Data Exchange (ETDEWEB)

    CLARK, D.L.

    1999-08-09

    Revision O was never issued. Finding safe and environmentally sound methods of storage and disposal of 54 million gallons of highly radioactive waste contained in 177 underground tanks is the largest challenge of Hanford cleanup. TWRS was established in 1991 and continues to integrate all aspects of the treatment and management of the high-level radioactive waste tanks. In fiscal Year 1997, program objectives were advanced in a number of areas. RL TWRS refocused the program toward retrieving, treating, and immobilizing the tank wastes, while maintaining safety as first priority. Moving from a mode of storing the wastes to getting the waste out of the tanks will provide the greatest cleanup return on the investment and eliminate costly mortgage continuance. There were a number of safety-related achievements in FY1997. The first high priority safety issue was resolved with the removal of 16 tanks from the ''Wyden Watch List''. The list, brought forward by Senator Ron Wyden of Oregon, identified various Hanford safety issues needing attention. One of these issues was ferrocyanide, a chemical present in 24 tanks. Although ferrocyanide can ignite at high temperature, analysis found that the chemical has decomposed into harmless compounds and is no longer a concern.

  6. 242-A Evaporator crystallizer facility integrated annual safety appraisal

    International Nuclear Information System (INIS)

    1991-01-01

    This report provides the results of the Fiscal Year (FY) 1991 Annual Integrated Safety Appraisal of the 242-A Evaporator Crystallizer Facility in the Hanford 200 East Area. The appraisal was conducted in December 1990 and January 1991, by the Waste Tank Safety Assurance (WTSA) organizations in conjunction with Radiological Engineering, Criticality Safety, Packaging and Shipping Safety, Emergency Preparedness, Environmental Compliance, and Quality Assurance. Reports of these eight organizations are presented as Sections 2 through 7 of this report. The purpose of the appraisal was to verify that the 242-A Evaporator meets US Department of Energy (DOE) and Westinghouse Hanford Company (WHC) requirements and current industry standards of good practice for the areas being appraised. A further purpose was to identify areas in which program effectiveness could be improved. In accordance with the guidance of WHC Management Requirements and Procedures (MRP)5.6, previously identified deficiencies which are being resolved by line management were not repeated as Findings or Observations unless progress or intended disposition was considered to be unsatisfactory

  7. Integrated model of port oil piping transportation system safety including operating environment threats

    OpenAIRE

    Kołowrocki, Krzysztof; Kuligowska, Ewa; Soszyńska-Budny, Joanna

    2017-01-01

    The paper presents an integrated general model of complex technical system, linking its multistate safety model and the model of its operation process including operating environment threats and considering variable at different operation states its safety structures and its components safety parameters. Under the assumption that the system has exponential safety function, the safety characteristics of the port oil piping transportation system are determined.

  8. Proposal of Integrated Safety Assessment Methodology for Embedded System

    International Nuclear Information System (INIS)

    Sun, Wei; Kageyama, Makoto; Kanemoto, Shigeru

    2011-01-01

    To do risk analysis and risk evaluation for complicated safety critical embedded systems, there are three things should be paid a good attention: 1) an efficient and integrated model expression of embedded systems: 2) systematic risk analysis based on integrated system model: 3) quantitative risk evaluation for software and hardware integrated system. In this paper, taken electric water boiler as a target system, a proposal of risk analysis and risk evaluation for the embedded system is presented to meet these three purposes. In risk analysis, MFM is used and FT is generated automatically from MFM following some rules: And in risk evaluation, GO-FLOW is used to evaluate the reliability of sensors. And furthermore, FIT is applied to evaluate the safety software logic based on the diversity design concept. Although the electric water boiler is a simple example, it includes the key components of the embedded system like sensors, actuators, and software component. So, the process of modeling, analysis, and evaluation could be applied to other kinds of complicated embedded systems

  9. Foundational development of an advanced nuclear reactor integrated safety code

    International Nuclear Information System (INIS)

    Clarno, Kevin; Lorber, Alfred Abraham; Pryor, Richard J.; Spotz, William F.; Schmidt, Rodney Cannon; Belcourt, Kenneth; Hooper, Russell Warren; Humphries, Larry LaRon

    2010-01-01

    This report describes the activities and results of a Sandia LDRD project whose objective was to develop and demonstrate foundational aspects of a next-generation nuclear reactor safety code that leverages advanced computational technology. The project scope was directed towards the systems-level modeling and simulation of an advanced, sodium cooled fast reactor, but the approach developed has a more general applicability. The major accomplishments of the LDRD are centered around the following two activities. (1) The development and testing of LIME, a Lightweight Integrating Multi-physics Environment for coupling codes that is designed to enable both 'legacy' and 'new' physics codes to be combined and strongly coupled using advanced nonlinear solution methods. (2) The development and initial demonstration of BRISC, a prototype next-generation nuclear reactor integrated safety code. BRISC leverages LIME to tightly couple the physics models in several different codes (written in a variety of languages) into one integrated package for simulating accident scenarios in a liquid sodium cooled 'burner' nuclear reactor. Other activities and accomplishments of the LDRD include (a) further development, application and demonstration of the 'non-linear elimination' strategy to enable physics codes that do not provide residuals to be incorporated into LIME, (b) significant extensions of the RIO CFD code capabilities, (c) complex 3D solid modeling and meshing of major fast reactor components and regions, and (d) an approach for multi-physics coupling across non-conformal mesh interfaces.

  10. Foundational development of an advanced nuclear reactor integrated safety code.

    Energy Technology Data Exchange (ETDEWEB)

    Clarno, Kevin (Oak Ridge National Laboratory, Oak Ridge, TN); Lorber, Alfred Abraham; Pryor, Richard J.; Spotz, William F.; Schmidt, Rodney Cannon; Belcourt, Kenneth (Ktech Corporation, Albuquerque, NM); Hooper, Russell Warren; Humphries, Larry LaRon

    2010-02-01

    This report describes the activities and results of a Sandia LDRD project whose objective was to develop and demonstrate foundational aspects of a next-generation nuclear reactor safety code that leverages advanced computational technology. The project scope was directed towards the systems-level modeling and simulation of an advanced, sodium cooled fast reactor, but the approach developed has a more general applicability. The major accomplishments of the LDRD are centered around the following two activities. (1) The development and testing of LIME, a Lightweight Integrating Multi-physics Environment for coupling codes that is designed to enable both 'legacy' and 'new' physics codes to be combined and strongly coupled using advanced nonlinear solution methods. (2) The development and initial demonstration of BRISC, a prototype next-generation nuclear reactor integrated safety code. BRISC leverages LIME to tightly couple the physics models in several different codes (written in a variety of languages) into one integrated package for simulating accident scenarios in a liquid sodium cooled 'burner' nuclear reactor. Other activities and accomplishments of the LDRD include (a) further development, application and demonstration of the 'non-linear elimination' strategy to enable physics codes that do not provide residuals to be incorporated into LIME, (b) significant extensions of the RIO CFD code capabilities, (c) complex 3D solid modeling and meshing of major fast reactor components and regions, and (d) an approach for multi-physics coupling across non-conformal mesh interfaces.

  11. Integrated deterministic and probabilistic safety assessment: Concepts, challenges, research directions

    International Nuclear Information System (INIS)

    Zio, Enrico

    2014-01-01

    Highlights: • IDPSA contributes to robust risk-informed decision making in nuclear safety. • IDPSA considers time-dependent interactions among component failures and system process. • Also, IDPSA considers time-dependent interactions among control and operator actions. • Computational efficiency by advanced Monte Carlo and meta-modelling simulations. • Efficient post-processing of IDPSA output by clustering and data mining. - Abstract: Integrated deterministic and probabilistic safety assessment (IDPSA) is conceived as a way to analyze the evolution of accident scenarios in complex dynamic systems, like nuclear, aerospace and process ones, accounting for the mutual interactions between the failure and recovery of system components, the evolving physical processes, the control and operator actions, the software and firmware. In spite of the potential offered by IDPSA, several challenges need to be effectively addressed for its development and practical deployment. In this paper, we give an overview of these and discuss the related implications in terms of research perspectives

  12. Integrated deterministic and probabilistic safety assessment: Concepts, challenges, research directions

    Energy Technology Data Exchange (ETDEWEB)

    Zio, Enrico, E-mail: enrico.zio@ecp.fr [Ecole Centrale Paris and Supelec, Chair on System Science and the Energetic Challenge, European Foundation for New Energy – Electricite de France (EDF), Grande Voie des Vignes, 92295 Chatenay-Malabry Cedex (France); Dipartimento di Energia, Politecnico di Milano, Via Ponzio 34/3, 20133 Milano (Italy)

    2014-12-15

    Highlights: • IDPSA contributes to robust risk-informed decision making in nuclear safety. • IDPSA considers time-dependent interactions among component failures and system process. • Also, IDPSA considers time-dependent interactions among control and operator actions. • Computational efficiency by advanced Monte Carlo and meta-modelling simulations. • Efficient post-processing of IDPSA output by clustering and data mining. - Abstract: Integrated deterministic and probabilistic safety assessment (IDPSA) is conceived as a way to analyze the evolution of accident scenarios in complex dynamic systems, like nuclear, aerospace and process ones, accounting for the mutual interactions between the failure and recovery of system components, the evolving physical processes, the control and operator actions, the software and firmware. In spite of the potential offered by IDPSA, several challenges need to be effectively addressed for its development and practical deployment. In this paper, we give an overview of these and discuss the related implications in terms of research perspectives.

  13. Methodology used in the integrated assessment of PIUS-600 safety

    International Nuclear Information System (INIS)

    Fullwood, R.; Higgins, J.; Kroegar, P.

    1993-01-01

    The revolutionary reactor design, PIUS-600 as described in the Preliminary Safety Analysis Report (PSID) was subjected to analysis consisting of Failure Modes, Effects and Criticality Analysis (FMECA), Hazards and Operability (HAZOP) analysis, and conventional engineering review of the stress, neutronics, thermal hydraulics, and corrosion. These results were integrated in the PIUS Intermediate Table (PIT) from which accident initiators and mitigators were identified and categorized into seven estimated frequency intervals. Accident consequences were classified as: CC-1, minor radiological release, CC-2, clad release, CC-3, major release. The systems were analyzed using event sequence diagrams (ESDs) and event trees (ETs). The resulting accident sequences of the ET, were categorized into Event conditions (ECs) based on initiator frequency and combinations of failures. System interactions were considered in the FMECAs, ESDs, ETs and in an interaction table that also identified system safety classifications

  14. Methodology used in the integrated assessment of PIUS-600 safety

    International Nuclear Information System (INIS)

    Fullwood, R.; Higgins, J.; Kroeger, P.

    1993-01-01

    The revolutionary reactor design, PIUS-600 as described in the Preliminary Safety Analysis Report (PSID) was subject to analyses consisting of Failure Modes. Effects and Criticality Analysis (FMECA), Hazards and Operability (HAZOP) analysis, and conventional engineering review of the stress, neutronics, thermal hydraulics, and corrosion. These results were integrated in the PIUS Intermediate Table (PIT) from which accident initiators and mitigators were identified and categorized into seven estimated frequency intervals. Accident consequences were classified as: CC-1, minor radiological release, CC-2, clad release, CC-3, major release. The systems were analyzed using event sequence diagrams (ESDs) and event trees (ETs). The resulting accident sequences of the ET, were categorized into Event conditions (ECs) based on initiator frequency and combinations of failures. System interactions were considered in the FMECAs, ESDs, ETs and in an interaction table that also identified system safety classifications

  15. Criticality safety considerations. Integral Monitored Retrievable Storage (MRS) Facility

    International Nuclear Information System (INIS)

    1986-09-01

    This report summarizes the criticality analysis performed to address criticality safety concerns and to support facility design during the conceptual design phase of the Monitored Retrievable Storage (MRS) Facility. The report addresses the criticality safety concerns, the design features of the facility relative to criticality, and the results of the analysis of both normal operating and hypothetical off-normal conditions. Key references are provided (Appendix C) if additional information is desired by the reader. The MRS Facility design was developed and the related analysis was performed in accordance with the MRS Facility Functional Design Criteria and the Basis for Design. The detailed description and calculations are documented in the Integral MRS Facility Conceptual Design Report. In addition to the summary portion of this report, explanatary notes for various terms, calculation methodology, and design parameters are presented in Appendix A. Appendix B provides a brief glossary of technical terms

  16. Advanced safety management systems for maintenance of pipeline integrity

    International Nuclear Information System (INIS)

    Borysiewicz, M.; Potempski, S.

    2005-01-01

    One of the duties of the pipeline's operator is to introduce means for protection of human safety and the environment. This should be reflected in preparation of comprehensive Risk Management System with its key element Activity Programme for Management of Pipeline Integrity. In the paper such programme has been described taking into account law regulations and practical activities undertaken in technologically advanced countries (mainly USA and EU), where such solutions are implemented in routine operations. Possible solutions of realization of all elements of the programme, as well as information on utilization of computer aided support have been also included. (authors)

  17. Integral reactor vessel related to power reactor safety

    International Nuclear Information System (INIS)

    Widart, J.; Scailteur, A.

    1978-01-01

    Integral design applied to PWR pressure vessels allows to reach a high level of safety because: 1) it presents a better balance of the material in the geometry, resulting in an improved stress level (mainly faulted condition loadings); 2) location and geometry of the welds are designed in order to get a very sound pressure boundary of the upper part of the vessel; 3) the new location and geometry of the welds allow an easy ISI in such a way that ambiguity surrounding defect size or locaton is practically suppressed. (author)

  18. The safety basis of the integral fast reactor program

    International Nuclear Information System (INIS)

    Pedersen, D.R.; Seidel, B.R.

    1990-01-01

    The Integral Fast Reactor (IFR) and metallic fuel have emerged as the US Department of Energy reference reactor concept and fuel system for the development of an advanced liquid-metal reactor. This article addresses the basic elements of the IFR reactor concept and focuses on the safety advances achieved by the IFR Program in the areas of (1) fuel performance, (2) superior local faults tolerance, (3) transient fuel performance, (4) fuel-failure mechanisms, (5) performance in anticipated transients without scram, (6) core-melt mitigation, and (7) actinide recycle

  19. DOE-RL Integrated Safety Management System Description

    International Nuclear Information System (INIS)

    SHOOP, D.S.

    2000-01-01

    The purpose of this Integrated Safety Management System Description (ISMSD) is to describe the U.S. Department of Energy (DOE), Richland Operations Office (RL) ISMS as implemented through the RL Integrated Management System (RIMS). This ISMSD does not impose additional requirements but rather provides an overview describing how various parts of the ISMS fit together. Specific requirements for each of the core functions and guiding principles are established in other implementing processes, procedures, and program descriptions that comprise RIMS. RL is organized to conduct work through operating contracts; therefore, it is extremely difficult to provide an adequate ISMS description that only addresses RL functions. Of necessity, this ISMSD contains some information on contractor processes and procedures which then require RL approval or oversight. This ISMSD does not purport to contain a full description of the contractors' ISM System Descriptions

  20. DOE-RL Integrated Safety Management System Description

    CERN Document Server

    Shoop, D S

    2000-01-01

    The purpose of this Integrated Safety Management System Description (ISMSD) is to describe the U.S. Department of Energy (DOE), Richland Operations Office (RL) ISMS as implemented through the RL Integrated Management System (RIMS). This ISMSD does not impose additional requirements but rather provides an overview describing how various parts of the ISMS fit together. Specific requirements for each of the core functions and guiding principles are established in other implementing processes, procedures, and program descriptions that comprise RIMS. RL is organized to conduct work through operating contracts; therefore, it is extremely difficult to provide an adequate ISMS description that only addresses RL functions. Of necessity, this ISMSD contains some information on contractor processes and procedures which then require RL approval or oversight. This ISMSD does not purport to contain a full description of the contractors' ISM System Descriptions.

  1. Evaluation of implementation an Integrated Safety and Preventive Maintenance System for Improving of Safety Indexes

    Directory of Open Access Journals (Sweden)

    I mohammadfam

    2014-03-01

    Full Text Available Accident analysis shows that one of the main reasons for accidents is non-integration of maintenance units with safety. Merging these two processes through an integrated system can reduce and or eliminate accidents, diseases, and environmental pollution. These issues lead to improvement in organizational performance, as well. The aim of this study is to design and establish an integrated system for obtaining the aforementioned goal. Integration was carried out at Nirou Moharreke Machine Tools Company via Structured System Analysis & Design Method (SSADM. In order to measure the effectiveness of the system, selected indexes were compared using statistical methods prior and after system establishment. Results show that the accident severity index reduced from 135.46 in 2010, to 43.85 in 2012. Moreover, system effectiveness improved equipment reliability and availability (e.g. reliability of the Pfeiffer Milling machine (P (t>50 increased from 0.89 in 2010, to 0.9 in 2012. This system by forecasting various failures, and planning and designing the required operations for preventing occurrence of these failures, plays an important role in improving safety conditions of equipment, and increasing organizational performance, and is capable of presenting an excellent accident prevention program.

  2. A comparison of integrated safety analysis and probabilistic risk assessment

    International Nuclear Information System (INIS)

    Damon, Dennis R.; Mattern, Kevin S.

    2013-01-01

    The U.S. Nuclear Regulatory Commission conducted a comparison of two standard tools for risk informing the regulatory process, namely, the Probabilistic Risk Assessment (PRA) and the Integrated Safety Analysis (ISA). PRA is a calculation of risk metrics, such as Large Early Release Frequency (LERF), and has been used to assess the safety of all commercial power reactors. ISA is an analysis required for fuel cycle facilities (FCFs) licensed to possess potentially critical quantities of special nuclear material. A PRA is usually more detailed and uses more refined models and data than an ISA, in order to obtain reasonable quantitative estimates of risk. PRA is considered fully quantitative, while most ISAs are typically only partially quantitative. The extension of PRA methodology to augment or supplant ISAs in FCFs has long been considered. However, fuel cycle facilities have a wide variety of possible accident consequences, rather than a few surrogates like LERF or core damage as used for reactors. It has been noted that a fuel cycle PRA could be used to better focus attention on the most risk-significant structures, systems, components, and operator actions. ISA and PRA both identify accident sequences; however, their treatment is quite different. ISA's identify accidents that lead to high or intermediate consequences, as defined in 10 Code of Federal Regulations (CFR) 70, and develop a set of Items Relied on For Safety (IROFS) to assure adherence to performance criteria. PRAs identify potential accident scenarios and estimate their frequency and consequences to obtain risk metrics. It is acceptable for ISAs to provide bounding evaluations of accident consequences and likelihoods in order to establish acceptable safety; but PRA applications usually require a reasonable quantitative estimate, and often obtain metrics of uncertainty. This paper provides the background, features, and methodology associated with the PRA and ISA. The differences between the

  3. Development and assessment of best estimate integrated safety analysis code

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Bub Dong; Lee, Young Jin; Hwang, Moon Kyu (and others)

    2007-03-15

    Improvement of the integrated safety analysis code MARS3.0 has been carried out and a multi-D safety analysis application system has been established. Iterative matrix solver and parallel processing algorithm have been introduced, and a LINUX version has been generated to enable MARS to run in cluster PCs. MARS variables and sub-routines have been reformed and modularised to simplify code maintenance. Model uncertainty analyses have been performed for THTF, FLECHT, NEPTUN, and LOFT experiments as well as APR1400 plant. Participations in international cooperation research projects such as OECD BEMUSE, SETH, PKL, BFBT, and TMI-2 have been actively pursued as part of code assessment efforts. The assessment, evaluation and experimental data obtained through international cooperation projects have been registered and maintained in the T/H Databank. Multi-D analyses of APR1400 LBLOCA, DVI Break, SLB, and SGTR have been carried out as a part of application efforts in multi-D safety analysis. GUI based 3D input generator has been developed for user convenience. Operation of the MARS Users Group (MUG) was continued and through MUG, the technology has been transferred to 24 organisations. A set of 4 volumes of user manuals has been compiled and the correction reports for the code errors reported during MARS development have been published.

  4. Development and assessment of best estimate integrated safety analysis code

    International Nuclear Information System (INIS)

    Chung, Bub Dong; Lee, Young Jin; Hwang, Moon Kyu

    2007-03-01

    Improvement of the integrated safety analysis code MARS3.0 has been carried out and a multi-D safety analysis application system has been established. Iterative matrix solver and parallel processing algorithm have been introduced, and a LINUX version has been generated to enable MARS to run in cluster PCs. MARS variables and sub-routines have been reformed and modularised to simplify code maintenance. Model uncertainty analyses have been performed for THTF, FLECHT, NEPTUN, and LOFT experiments as well as APR1400 plant. Participations in international cooperation research projects such as OECD BEMUSE, SETH, PKL, BFBT, and TMI-2 have been actively pursued as part of code assessment efforts. The assessment, evaluation and experimental data obtained through international cooperation projects have been registered and maintained in the T/H Databank. Multi-D analyses of APR1400 LBLOCA, DVI Break, SLB, and SGTR have been carried out as a part of application efforts in multi-D safety analysis. GUI based 3D input generator has been developed for user convenience. Operation of the MARS Users Group (MUG) was continued and through MUG, the technology has been transferred to 24 organisations. A set of 4 volumes of user manuals has been compiled and the correction reports for the code errors reported during MARS development have been published

  5. Integrated Safety, Environmental and Emergency Management System (ISEEMS)

    International Nuclear Information System (INIS)

    Silver, R.; Langwell, G.; Thomas, C.; Coffing, S.

    1996-01-01

    The Risk Management and NEPA (National Environmental Policy Act) Department of Sandia National Laboratories/New Mexico (SNL/NM) recognized the need for hazard and environmental data analysis and management to support the line managers' need to know, understand, manage and document the hazards in their facilities and activities. The Integrated Safety, Environmental, and Emergency Management System (ISEEMS) was developed in response to this need. SNL needed a process that would quickly and easily determine if a facility or project activity contained only standard industrial hazards and therefore require minimal safety documentation, or if non-standard industrial hazards existed which would require more extensive analysis and documentation. Many facilities and project activities at SNL would benefit from the quick screening process used in ISEEMS. In addition, a process was needed that would expedite the NEPA process. ISEEMS takes advantage of the fact that there is some information needed for the NEPA process that is also needed for the safety documentation process. The ISEEMS process enables SNL line organizations to identify and manage hazards and environmental concerns at a level of effort commensurate with the hazards themselves by adopting a necessary and sufficient (graded) approach to compliance. All hazard-related information contained within ISEEMS is location based and can be displayed using on-line maps and building floor plans. This visual representation provides for quick assimilation and analysis

  6. Integrated risk management of safety and development on transportation corridors

    International Nuclear Information System (INIS)

    Thekdi, Shital A.; Lambert, James H.

    2015-01-01

    Prioritization of investments to protect safety and performance of multi-regional transportation networks from adjacent land development is a key concern for infrastructure agencies, land developers, and other stakeholders. Despite ample literature describing relationships between transportation and land use, no evidence-based methods exist for monitoring corridor needs on a large scale. Risk analysis is essential to the preservation of system safety and capacity, including avoidance of costly retrofits, regret, and belated action. This paper introduces the Corridor Trace Analysis (CTA) for prioritizing corridor segments that are vulnerable to adjacent land development. The method integrates several components: (i) estimation of likelihood of adjacent land development, using influence diagram and rule-based modeling, (ii) characterization of access point density using geospatial methods, and (iii) plural-model evaluation of corridors, monitoring indices of land development likelihood, access point densities, and traffic volumes. The results inform deployment of options that include closing access points, restricting development, and negotiation of agencies and developers. The CTA method is demonstrated on a region encompassing 6000 centerline miles (about 10,000 km) of transportation corridors. The method will be of interest to managers investing in safety and performance of infrastructure systems, balancing safety, financial, and other criteria of concern for diverse stakeholders. - Highlights: • The Corridor Trace Analysis (CTA) method for prioritizing transportation corridors. • The CTA method studies corridors vulnerable to adjacent land development. • The CTA method quantifies the influence of risk scenarios on agency priorities. • The CTA method is demonstrated on 6000 miles of critical transportation corridor

  7. B plant/WESF integrated annual safety appraisal

    International Nuclear Information System (INIS)

    Anderson, J.K.

    1990-12-01

    This report provides the results of the Fiscal Year 1990 Annual Integrated Safety Appraisal of the B Plant and Waste Encapsulation and Storage Facility in the Hanford Site 200 East Area. The appraisal was conducted in August and September 1990, by the Defense Waste Disposal Safety group, in conjunction with Health Physics and Emergency Preparedness. Reports of these three organizations for their areas of responsibility are presented. The purpose of the appraisal was to determine if the areas being appraised meet US Department of Energy (DOE) and Westinghouse Hanford Company (WHC) requirements and current industry standards of good practice. A further purpose was to identify areas in which program effectiveness could be improved. In accordance with the guidance of WHC Management Requirements and Procedures 5.6, previously identified deficiencies which are being resolved by line management were not repeated as Findings or Observations unless progress or intended disposition was considered to be unsatisfactory. The overall assessment is that there are no major safety problems associated with current operations. Programs are in place to provide the necessary safety controls, evaluations, overviews, and support. In most respects these programs are being implemented effectively. However, there are a number of deficiencies in details of program design and implementation. The appraisal identified a total of 23 Findings and 27 Observations of deficiencies. All Observations are Seriousness Category 3. Fifteen Findings were Category 2 and 8 were Category 3. Most of the Category 2 Findings were so categorized on the basis of noncompliance with mandatory DOE Orders or WHC policies and procedures, rather than potential risk to personnel

  8. Spent Nuclear Fuel (SNF) project Integrated Safety Management System phase I and II Verification Review Plan

    International Nuclear Information System (INIS)

    CARTER, R.P.

    1999-01-01

    The U.S. Department of Energy (DOE) commits to accomplishing its mission safely. To ensure this objective is met, DOE issued DOE P 450.4, Safety Management System Policy, and incorporated safety management into the DOE Acquisition Regulations ([DEAR] 48 CFR 970.5204-2 and 90.5204-78). Integrated Safety Management (ISM) requires contractors to integrate safety into management and work practices at all levels so that missions are achieved while protecting the public, the worker, and the environment. The contractor is required to describe the Integrated Safety Management System (ISMS) to be used to implement the safety performance objective

  9. Spent Nuclear Fuel (SNF) project Integrated Safety Management System phase I and II Verification Review Plan

    Energy Technology Data Exchange (ETDEWEB)

    CARTER, R.P.

    1999-11-19

    The U.S. Department of Energy (DOE) commits to accomplishing its mission safely. To ensure this objective is met, DOE issued DOE P 450.4, Safety Management System Policy, and incorporated safety management into the DOE Acquisition Regulations ([DEAR] 48 CFR 970.5204-2 and 90.5204-78). Integrated Safety Management (ISM) requires contractors to integrate safety into management and work practices at all levels so that missions are achieved while protecting the public, the worker, and the environment. The contractor is required to describe the Integrated Safety Management System (ISMS) to be used to implement the safety performance objective.

  10. Safety evaluation of socket weld integrity in nuclear piping

    International Nuclear Information System (INIS)

    Choi, Y.H.; Kim, H.J.; Choi, S.Y.; Kim, Y.J.; Kim, Y.J.

    2004-01-01

    The purposes of this paper are to evaluate the integrity of socket weld in nuclear piping and prepare the technical basis for a new guideline on radiographic testing (RT) for the socket weld. Recently, the integrity of the socket weld is regarded as a safety concern in nuclear power plants because lots of failures and leaks have been reported in the socket weld. The root causes of the socket weld failure are known as unanticipated loadings such as vibration or thermal fatigue and improper weld joint during construction. The ASME Code sec. III requires 1/16 inch gap between the pipe and fitting in the socket weld. Many failure cases, however, showed that the gap requirement was not satisfied. The Code also requires magnetic particle examination (MT) or liquid penetration examination (PT) on the socket weld, but not radiographic examination (RT). It means that it is not easy to examine the 1/16 inch gap in the socket weld by using the NDE methods currently required in the Code. In this paper, the effects of the requirements in the ASME Code sec. III on the socket weld integrity were evaluated by using finite element method. The crack behavior in the socket weld was also investigated under vibration event in nuclear power plants. The results showed that the socket weld was very susceptible to the vibration if the requirements in ASME Code were not satisfied. The constraint between the pipe and fitting due to the contact significantly affects the integrity of the socket weld. This paper also suggests a new guideline on the RT for the socket weld during construction stage in nuclear power plants. (orig.)

  11. Integrity of Safety-Related Fast Reactor Structures

    International Nuclear Information System (INIS)

    Rose, R.T.; Tomkins, B.

    1981-01-01

    The LMFBR contains several structural items whose integrity must be safeguarded during the life of the plant. These items include the main core support structures (strongback, diagrid) and the primary tank to which these structures are attached. In order to demonstrate an acceptable level of structural integrity, the chosen design philosophy must be supported by both analytical and experimental evidence. This paper describes the current approaches in the UK to these requirements. Section 2 describes the materials mechanical properties tests performed to date on both fracture toughness and fatigue crack growth in Type 316 austenitic stainless steel plate and weldments. This data illustrates the problems in identifying the relevant materials fracture parameters for use in assessments. Section 3 shows the test programmes in hand to extend the materials programmes to tests on structural features (mainly welded wide plate tests) which incorporate the complexity of weldments in a structural context. This includes experimental evidence on the effects of local weld residual stresses on structural failure. Various routes are open for the integrity assessment of FR structures. These are discussed in Section 4 but in effect they reduce to a fracture mechanics approach using some technique to cope with elastic-plastic fracture. The main problems at present relate to our ability in analysis to cope with residual stresses and the post-initiation region of the fracture resistance curve. Also, there is the problem of initial defect sizing by current NDE techniques. Current conservative analytical assessments give acceptable defect sizes of order a few millimetres in irradiated weldments. Finally, Section 5 discusses the options open in design to cope with safety related structures under normal and abnormal loading conditions. It is clear that several options exist in design to satisfy the demand for high integrity

  12. Translational safety biomarkers of colonic barrier integrity in the rat.

    Science.gov (United States)

    Erkens, Tim; Bueters, Ruud; van Heerden, Marjolein; Cuyckens, Filip; Vreeken, Rob; Goeminne, Nick; Lammens, Lieve

    2018-05-20

    The intestinal barrier controls intestinal permeability, and its disruption has been associated with multiple diseases. Therefore, preclinical safety biomarkers monitoring barrier integrity are essential during the development of drugs targeting the intestines, particularly if starting treatment early after onset of disease. Classical toxicology endpoints are not sensitive enough and therefore our objective was to identify non-invasive markers enabling early in vivo detection of colonic barrier perturbation. Male Sprague-Dawley rats were dosed intracolonically via the rectum, using sodium caprate or ibuprofen as tool compounds to alter barrier integrity. Several potentially translational biomarkers and probe molecules related to permeability, inflammation or tissue damage were evaluated, using various analytical platforms, including immunoassays, targeted metabolomics and highly sensitive ultra-performance liquid chromatography-tandem mass spectrometry. Several markers were identified that allow early in vivo detection of colonic barrier integrity changes, before histopathological evidence of tissue damage. The most promising permeability markers identified were plasma fluorescein isothiocyanate-dextran 4000 and a lactulose/mannitol/sucralose mixture in urine. These markers showed maximum increases over 100-fold or approximately 10-50-fold, respectively. Intracolonic administration of the above probe molecules outperformed oral administration and inflammatory or other biomarkers, such as α 2 -macroglobulin, calprotectin, cytokines, prostaglandins and a panel of metabolic molecules to identify early and subtle changes in barrier integrity. However, optimal timing of probe administration and sample collection is important for all markers evaluated. Inclusion of these probe molecules in preclinical toxicity studies might aid in risk assessment and the design of a clinical biomarker plan, as several of these markers have translational potential. Copyright © 2018 John

  13. PANDA: A Multipurpose Integral Test Facility for LWR Safety Investigations

    International Nuclear Information System (INIS)

    Paladino, D.; Dreier, J.

    2012-01-01

    The PANDA facility is a large scale, multicompartmental thermal hydraulic facility suited for investigations related to the safety of current and advanced LWRs. The facility is multipurpose, and the applications cover integral containment response tests, component tests, primary system tests, and separate effect tests. Experimental investigations carried on in the PANDA facility have been embedded in international projects, most of which under the auspices of the EU and OECD and with the support of a large number of organizations (regulatory bodies, technical dupport organizations, national laboratories, electric utilities, industries) worldwide. The paper provides an overview of the research programs performed in the PANDA facility in relation to BWR containment systems and those planned for PWR containment systems.

  14. 75 FR 15485 - Pipeline Safety: Workshop on Guidelines for Integrity Assessment of Cased Pipe

    Science.gov (United States)

    2010-03-29

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket ID...: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice of workshop. SUMMARY... ``Guidelines for Integrity Assessment of Cased Pipe in Gas Transmission Pipelines'' and related Frequently...

  15. 75 FR 5244 - Pipeline Safety: Integrity Management Program for Gas Distribution Pipelines; Correction

    Science.gov (United States)

    2010-02-02

    ... Management Program for Gas Distribution Pipelines; Correction AGENCY: Pipeline and Hazardous Materials Safety... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration 49 CFR Part... Regulations to require operators of gas distribution pipelines to develop and implement integrity management...

  16. AN ADVANCED TOOL FOR APPLIED INTEGRATED SAFETY MANAGEMENT

    Energy Technology Data Exchange (ETDEWEB)

    Potts, T. Todd; Hylko, James M.; Douglas, Terence A.

    2003-02-27

    WESKEM, LLC's Environmental, Safety and Health (ES&H) Department had previously assessed that a lack of consistency, poor communication and using antiquated communication tools could result in varying operating practices, as well as a failure to capture and disseminate appropriate Integrated Safety Management (ISM) information. To address these issues, the ES&H Department established an Activity Hazard Review (AHR)/Activity Hazard Analysis (AHA) process for systematically identifying, assessing, and controlling hazards associated with project work activities during work planning and execution. Depending on the scope of a project, information from field walkdowns and table-top meetings are collected on an AHR form. The AHA then documents the potential failure and consequence scenarios for a particular hazard. Also, the AHA recommends whether the type of mitigation appears appropriate or whether additional controls should be implemented. Since the application is web based, the information is captured into a single system and organized according to the >200 work activities already recorded in the database. Using the streamlined AHA method improved cycle time from over four hours to an average of one hour, allowing more time to analyze unique hazards and develop appropriate controls. Also, the enhanced configuration control created a readily available AHA library to research and utilize along with standardizing hazard analysis and control selection across four separate work sites located in Kentucky and Tennessee. The AHR/AHA system provides an applied example of how the ISM concept evolved into a standardized field-deployed tool yielding considerable efficiency gains in project planning and resource utilization. Employee safety is preserved through detailed planning that now requires only a portion of the time previously necessary. The available resources can then be applied to implementing appropriate engineering, administrative and personal protective equipment

  17. Nuclear Safeguards Infrastructure Development and Integration with Safety and Security

    International Nuclear Information System (INIS)

    Kovacic, Donald N.; Raffo-Caiado, Ana Claudia; McClelland-Kerr, John; Van sickle, Matthew; Bissani, Mo

    2009-01-01

    Faced with increasing global energy demands, many developing countries are considering building their first nuclear power plant. As a country embarks upon or expands its nuclear power program, it should consider how it will address the 19 issues laid out in the International Atomic Energy Agency (IAEA) document Milestones in Development of a National Infrastructure for Nuclear Power. One of those issues specifically addresses the international nonproliferation treaties and commitments and the implementation of safeguards to prevent diversion of nuclear material from peaceful purposes to nuclear weapons. Given the many legislative, economic, financial, environmental, operational, and other considerations preoccupying their planners, it is often difficult for countries to focus on developing the core strengths needed for effective safeguards implementation. Typically, these countries either have no nuclear experience or it is limited to the operation of research reactors used for radioisotope development and scientific research. As a result, their capacity to apply safeguards and manage fuel operations for a nuclear power program is limited. This paper argues that to address the safeguards issue effectively, a holistic approach must be taken to integrate safeguards with the other IAEA issues including safety and security - sometimes referred to as the '3S' concept. Taking a holistic approach means that a country must consider safeguards within the context of its entire nuclear power program, including operations best practices, safety, and security as well as integration with its larger nonproliferation commitments. The Department of Energy/National Nuclear Security Administration's International Nuclear Safeguards and Engagement Program (INSEP) has been involved in bilateral technical cooperation programs for over 20 years to promote nonproliferation and the peaceful uses of nuclear energy. INSEP is currently spearheading efforts to promote the development of

  18. LOFT integral test system final safety analysis report

    International Nuclear Information System (INIS)

    1974-03-01

    Safety analyses are presented for the following LOFT Reactor systems: engineering safety features; support buildings and facilities; instrumentation and controls; electrical systems; and auxiliary systems. (JWR)

  19. Integrated model of port oil piping transportation system safety including operating environment threats

    Directory of Open Access Journals (Sweden)

    Kołowrocki Krzysztof

    2017-06-01

    Full Text Available The paper presents an integrated general model of complex technical system, linking its multistate safety model and the model of its operation process including operating environment threats and considering variable at different operation states its safety structures and its components safety parameters. Under the assumption that the system has exponential safety function, the safety characteristics of the port oil piping transportation system are determined.

  20. Food safety objective: an integral part of food chain management

    NARCIS (Netherlands)

    Gorris, L.G.M.

    2005-01-01

    The concept of food safety objective has been proposed to provide a target for operational food safety management, leaving flexibility in the way equivalent food safety levels are achieved by different food chains. The concept helps to better relate operational food safety management to public

  1. Development of Network Protocol for the Integrated Safety System

    Energy Technology Data Exchange (ETDEWEB)

    Park, S. W.; Baek, J. I.; Lee, S. H.; Park, C. S.; Park, K. H.; Shin, J. M. [Hannam Univ., Daejeon (Korea, Republic of)

    2007-06-15

    Communication devices in the safety system of nuclear power plants are distinguished from those developed for commercial purposes in terms of a strict requirement of safety. The concept of safety covers the determinability, the reliability, and the separation/isolation to prevent the undesirable interactions among devices. The safety also requires that these properties be never proof less. Most of the current commercialized communication products rarely have the safety properties. Moreover, they can be neither verified nor validated to satisfy the safety property of implementation process. This research proposes the novel architecture and protocol of a data communication network for the safety system in nuclear power plants.

  2. Development of Network Protocol for the Integrated Safety System

    International Nuclear Information System (INIS)

    Park, S. W.; Baek, J. I.; Lee, S. H.; Park, C. S.; Park, K. H.; Shin, J. M.

    2007-06-01

    Communication devices in the safety system of nuclear power plants are distinguished from those developed for commercial purposes in terms of a strict requirement of safety. The concept of safety covers the determinability, the reliability, and the separation/isolation to prevent the undesirable interactions among devices. The safety also requires that these properties be never proof less. Most of the current commercialized communication products rarely have the safety properties. Moreover, they can be neither verified nor validated to satisfy the safety property of implementation process. This research proposes the novel architecture and protocol of a data communication network for the safety system in nuclear power plants

  3. Online Dispatching Rules For Vehicle-Based Internal Transport Systems

    NARCIS (Netherlands)

    T. Le-Anh (Tuan); M.B.M. de Koster (René)

    2004-01-01

    textabstractOn-line vehicles dispatching rules are widely used in many facilities such as warehouses to control vehicles' movements. Single-attribute dispatching rules, which dispatch vehicles based on only one parameter, are used commonly. However, multi-attribute dispatching rules prove to be

  4. Integrated system of safety features for spent fuel interim storage

    International Nuclear Information System (INIS)

    Pantazi, Doina; Stanciu, Marcela; Mateescu, Silvia; Marin, Ion

    1999-01-01

    The design of the spent fuel interim storage facility (SFISF) must meet the applicable safety requirements in order to ensure radiological protection of the personnel, public and environment during all phases of the facility. To elaborate the safety documentation necessary for licensing, we were trying to chose the most appropriate approach related to safety features for SFISF, based on national and international regulations, standards and recommendations, as well as on the experience of other countries with similar facilities and finally, on our own experience in designing other nuclear objectives in Romania. The paper presents the issues that we consider important for the safety evaluation and are developed as a detailed diagram. The diagram contains in a logical succession the following issues: - fundamental principles of radioprotection; - fundamental safety principles of radioactive waste management; - safety objectives of SFISF; - safety criteria for SFISF; - safety requirements for SFISF; - siting criteria for SFISF; - siting requirements for SFISF. (authors)

  5. Guidelines for the review research reactor safety. Reference document for IAEA Integrated Safety Assessment of Research Reactors (INSARR)

    International Nuclear Information System (INIS)

    1997-01-01

    In 1992, the IAEA published new safety standards for research reactors as part of the set of publications considered by its Research Reactor Safety Programme (RRSP). This set also includes publications giving guidance for all safety aspects related to the lifetime of a research reactor. In addition, the IAEA has also revised the Safety Standards for radiation protection. Consequently, it was considered advisable to revise the Integrated Safety Assessment of Research Reactors (INSARR) procedures to incorporate the new requirements and guidance as well as to extend the scope of the safety reviews to currently operating research reactors. The present report is the result of this revision. The purpose of this report is to give guidance on the preparation, execution, reporting and follow-up of safety review mission to research reactors as conducted by the IAEA under its INSARR missions safety service. However, it will also be of assistance to operators and regulators in conducting: (a) ad hoc safety assessments of research reactors to address individual issues such as ageing or safety culture; and (b) other types of safety reviews such as internal and peer reviews and regulatory inspections

  6. Development and application of an integrated evaluation framework for preventive safety applications

    NARCIS (Netherlands)

    Scholliers, J.; Joshi, S.; Gemou, M.; Hendriks, F.; Ljung Aust, M.; Luoma, J.; Netto, M.; Engstrom, J.; Leanderson Olsson, S.; Kutzner, R.; Tango, F.; Amditis, A.J.; Blosseville, J.M.; Bekiaris, E.

    2011-01-01

    Preventive safety functions help drivers avoid or mitigate accidents. No quantitative methods have been available to evaluate the safety impact of these systems. This paper describes a framework for the assessment of preventive and active safety functions, which integrates procedures for technical

  7. 75 FR 56112 - Integrated Food Safety System Online Collaboration Development-Cooperative Agreement With the...

    Science.gov (United States)

    2010-09-15

    ... FDA to meet the White House Food Safety Working Group recommendation that the Federal government... development of an integrated food safety system, and the development and implementation of a sustainable model... levels. NCFPD also has past experience directly supporting the White House Food Safety Working Group...

  8. Evaluating and Predicting Patient Safety for Medical Devices With Integral Information Technology

    Science.gov (United States)

    2005-01-01

    323 Evaluating and Predicting Patient Safety for Medical Devices with Integral Information Technology Jiajie Zhang, Vimla L. Patel, Todd R...errors are due to inappropriate designs for user interactions, rather than mechanical failures. Evaluating and predicting patient safety in medical ...the users on the identified trouble spots in the devices. We developed two methods for evaluating and predicting patient safety in medical devices

  9. Integrated Safety Management System Phase I Verification for the Plutonium Finishing Plant (PFP) [VOL 1 & 2

    Energy Technology Data Exchange (ETDEWEB)

    SETH, S.S.

    2000-01-10

    U.S. Department of Energy (DOE) Policy 450.4, Safety Management System Policy commits to institutionalizing an Integrated Safety Management System (ISMS) throughout the DOE complex as a means of accomplishing its missions safely. DOE Acquisition Regulation 970.5204-2 requires that contractors manage and perform work in accordance with a documented safety management system.

  10. Integrated Environment and Safety and Health Management System (ISMS) Implementation Project Plan

    Energy Technology Data Exchange (ETDEWEB)

    MITCHELL, R.L.

    2000-01-10

    The Integrated Environment, Safety and Health Management System (ISMS) Implementation Project Plan serves as the project document to guide the Fluor Hanford, Inc (FHI) and Major Subcontractor (MSC) participants through the steps necessary to complete the integration of environment, safety, and health into management and work practices at all levels.

  11. 49 CFR 1106.3 - Actions for which Safety Integration Plan is required.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 8 2010-10-01 2010-10-01 false Actions for which Safety Integration Plan is required. 1106.3 Section 1106.3 Transportation Other Regulations Relating to Transportation (Continued... TRANSPORTATION BOARD CONSIDERATION OF SAFETY INTEGRATION PLANS IN CASES INVOLVING RAILROAD CONSOLIDATIONS...

  12. 49 CFR 244.11 - Contents of a Safety Integration Plan.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 4 2010-10-01 2010-10-01 false Contents of a Safety Integration Plan. 244.11 Section 244.11 Transportation Other Regulations Relating to Transportation (Continued) FEDERAL RAILROAD ADMINISTRATION, DEPARTMENT OF TRANSPORTATION REGULATIONS ON SAFETY INTEGRATION PLANS GOVERNING RAILROAD...

  13. 78 FR 32010 - Pipeline Safety: Public Workshop on Integrity Verification Process

    Science.gov (United States)

    2013-05-28

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... Hazardous Materials Safety Administration, DOT. ACTION: Notice of public meeting. SUMMARY: This notice is announcing a public workshop to be held on the concept of ``Integrity Verification Process.'' The Integrity...

  14. Integrated Environment and Safety and Health Management System (ISMS) Implementation Project Plan

    International Nuclear Information System (INIS)

    MITCHELL, R.L.

    2000-01-01

    The Integrated Environment, Safety and Health Management System (ISMS) Implementation Project Plan serves as the project document to guide the Fluor Hanford, Inc (FHI) and Major Subcontractor (MSC) participants through the steps necessary to complete the integration of environment, safety, and health into management and work practices at all levels

  15. Implementation Science: New Approaches to Integrating Quality and Safety Education for Nurses Competencies in Nursing Education.

    Science.gov (United States)

    Dolansky, Mary A; Schexnayder, Julie; Patrician, Patricia A; Sales, Anne

    Although quality and safety competencies were developed and disseminated nearly a decade ago by the Quality and Safety Education for Nurses (QSEN) project, the uptake in schools of nursing has been slow. The use of implementation science methods may be useful to accelerate quality and safety competency integration in nursing education. The article includes a definition and description of implementation science methods and practical implementation strategies for nurse educators to consider when integrating the QSEN competencies into nursing curriculum.

  16. Leader communication approaches and patient safety: An integrated model.

    Science.gov (United States)

    Mattson, Malin; Hellgren, Johnny; Göransson, Sara

    2015-06-01

    Leader communication is known to influence a number of employee behaviors. When it comes to the relationship between leader communication and safety, the evidence is more scarce and ambiguous. The aim of the present study is to investigate whether and in what way leader communication relates to safety outcomes. The study examines two leader communication approaches: leader safety priority communication and feedback to subordinates. These approaches were assumed to affect safety outcomes via different employee behaviors. Questionnaire data, collected from 221 employees at two hospital wards, were analyzed using structural equation modeling. The two examined communication approaches were both positively related to safety outcomes, although leader safety priority communication was mediated by employee compliance and feedback communication by organizational citizenship behaviors. The findings suggest that leader communication plays a vital role in improving organizational and patient safety and that different communication approaches seem to positively affect different but equally essential employee safety behaviors. The results highlights the necessity for leaders to engage in one-way communication of safety values as well as in more relational feedback communication with their subordinates in order to enhance patient safety. Copyright © 2015 Elsevier Ltd. and National Safety Council. Published by Elsevier Ltd. All rights reserved.

  17. Integrated safety analysis to operate while constructing Urenco USA

    International Nuclear Information System (INIS)

    Kohrt, Rick; Su, Shiaw-Der; Lehman, Richard

    2013-01-01

    The URENCO USA (UUSA) site in Lea County, New Mexico, USA is authorized by the U.S. Nuclear Regulatory Commission (NRC) for construction and operation of a uranium enrichment facility under 10 CFR 70 (Ref 1). The facility employs the gas centrifuge process to separate natural uranium hexafluoride (UF 6 ) feed material into a product stream enriched up to 5% U-235 and a depleted UF 6 stream containing approximately 0.2 to 0.34% U-235. Initial plant operations, with a limited number of cascades on line, commenced in the second half of 2010. Construction activities continue as each subsequent cascade is commissioned and placed into service. UUSA performed an Integrated Safety Analysis (ISA) to allow the facility to operate while constructing the remainder of the facility. The ISA Team selected the What-If/Checklist method based on guidance in NUREG-1513 (Ref 2) and AIChE Guidelines (Ref 3). Of the three methods recommended for high risk events HAZOP, What-If/Checklist, or Failure Modes and Effects Analysis (FMEA), the What-If/Checklist lends itself best to construction activities. It combines the structure of a checklist with an unstructured 'brainstorming' approach to create a list of specific accident events that could produce an undesirable consequence. The What-If/Checklist for Operate While Constructing divides the UUSA site into seven areas and creates what-if questions for sixteen different construction activities, such as site preparation, external construction cranes, and internal construction lifts. The result is a total of 112 nodes, for which the Operate While Constructing ISA Team created hundreds of what-if questions. For each what-if question the team determined the likelihood, consequences, safeguards, and acceptability of risk. What-if questions with unacceptable risk are the accident sequences and their selected safeguards are the Items Relied on For Safety (IROFS). The final ISA identified four (4) new accident sequences that, unless

  18. APMS: An Integrated Set of Tools for Measuring Safety

    Science.gov (United States)

    Statler, Irving C.; Reynard, William D. (Technical Monitor)

    1996-01-01

    statistical evaluation of the performance of large groups of flights. This paper describes the integrated suite of tools that will assist analysts in evaluating the operational performance and safety of the national air transport system, the air carrier, and the air crew.

  19. Mechatronics design and experimental verification of an electric-vehicle-based hybrid thermal management system

    Directory of Open Access Journals (Sweden)

    Yi-Hsuan Hung

    2016-02-01

    Full Text Available In this study, an electric-vehicle-based thermal management system was designed for dual energy sources. An experimental platform developed in a previous study was modified. Regarding the mechanical components, a heat exchanger with a radiator, proportional valve, coolant pipes, and coolant pump was appropriately integrated. Regarding the electric components, two heaters emulating waste heat were controlled using two programmable power supply machines. A rapid-prototyping controller with two temperature inputs and three outputs was designed. Rule-based control strategies were coded to maintain optimal temperatures for the emulated proton exchange membrane fuel cells and lithium batteries. To evaluate the heat power of dual energy sources, driving cycles, energy management control, and efficiency maps of energy sources were considered for deriving time-variant values. The main results are as follows: (a an advanced mechatronics platform was constructed; (b a driving cycle simulation was successfully conducted; and (c coolant temperatures reached their optimal operating ranges when the proportional valve, radiator, and coolant pump were sequentially controlled. The benefits of this novel electric-vehicle-based thermal management system are (a high-efficiency operation of energy sources, (b low occupied volume integrated with energy sources, and (c higher electric vehicle traveling mileage. This system will be integrated with real energy sources and a real electric vehicle in the future.

  20. Research on integrated managing system based on CIMS for nuclear power plant safety

    International Nuclear Information System (INIS)

    Zhou Gang

    2006-01-01

    In order to improve safety, economy and reliability of operation for nuclear power plant (NPP), a novel integrated managing method was proposed based on the ideas of computer and contemporary integrated manufacturing system (CIMS). The application of CIMS to nuclear power plant safety management was researched. In order to design an integrated managing system to meet the needs of NPP safety management, all work related to nuclear safety is divided into different category according to its characters. On basis of this work, general integrated managing system was designed at first. Then subsystems were designed and every subsystem implements a category of nuclear safety management work. All subsystems are independent relatively on the one hand and are interrelated on other hand by global information system. (authors)

  1. Addressing Uniqueness and Unison of Reliability and Safety for a Better Integration

    Science.gov (United States)

    Huang, Zhaofeng; Safie, Fayssal

    2016-01-01

    Over time, it has been observed that Safety and Reliability have not been clearly differentiated, which leads to confusion, inefficiency, and, sometimes, counter-productive practices in executing each of these two disciplines. It is imperative to address this situation to help Reliability and Safety disciplines improve their effectiveness and efficiency. The paper poses an important question to address, "Safety and Reliability - Are they unique or unisonous?" To answer the question, the paper reviewed several most commonly used analyses from each of the disciplines, namely, FMEA, reliability allocation and prediction, reliability design involvement, system safety hazard analysis, Fault Tree Analysis, and Probabilistic Risk Assessment. The paper pointed out uniqueness and unison of Safety and Reliability in their respective roles, requirements, approaches, and tools, and presented some suggestions for enhancing and improving the individual disciplines, as well as promoting the integration of the two. The paper concludes that Safety and Reliability are unique, but compensating each other in many aspects, and need to be integrated. Particularly, the individual roles of Safety and Reliability need to be differentiated, that is, Safety is to ensure and assure the product meets safety requirements, goals, or desires, and Reliability is to ensure and assure maximum achievability of intended design functions. With the integration of Safety and Reliability, personnel can be shared, tools and analyses have to be integrated, and skill sets can be possessed by the same person with the purpose of providing the best value to a product development.

  2. Curriculum: Integrating Health and Safety Into Engineering Curricula.

    Science.gov (United States)

    Talty, John T.

    1985-01-01

    National Institute for Occupational Safety and Health instituted a project in 1980 to encourage engineering educators to focus on occupational safety and health issues in engineering curricula. Progress to date is outlined, considering specific results in curriculum development, engineering society interaction, and formation of a teaching…

  3. Integrating system safety into the basic systems engineering process

    Science.gov (United States)

    Griswold, J. W.

    1971-01-01

    The basic elements of a systems engineering process are given along with a detailed description of what the safety system requires from the systems engineering process. Also discussed is the safety that the system provides to other subfunctions of systems engineering.

  4. Systems engineering applied to integrated safety management for high consequence facilities

    International Nuclear Information System (INIS)

    Barter, R; Morais, B.

    1998-01-01

    Integrated Safety Management is a concept that is being actively promoted by the U.S. Department of Energy as a means of assuring safe operation of its facilities. The concept involves the integration of safety precepts into work planning rather than adjusting for safe operations after defining the work activity. The system engineering techniques used to design an integrated safety management system for a high consequence research facility are described. An example is given to show how the concepts evolved with the system design

  5. Rad waste disposal safety analysis / Integrated safety assessment of a waste repository

    International Nuclear Information System (INIS)

    Jeong, Jongtae; Choi, Jongwon; Kang, Chulhyung

    2012-04-01

    We developed CYPRUS+and adopted PID and RES method for the development of scenario. Safety performance assessment program was developed using GoldSim for the safety assessment of disposal system for the disposal of spnet fuels and wastes resulting from the pyrpoprocessing. Biosphere model was developed and verified in cooperation with JAEA. The capability to evaluate post-closure performance and safety was added to the previously developed program. And, nuclide migration and release to the biosphere considering site characteristics was evaluated by using deterministic and probabilistic approach. Operational safety assessment for drop, fire, and earthquake was also statistically evaluated considering well-established input parameter distribution. Conservative assessment showed that dose rate is below the limit value of low- and intermediate-level repository. Gas generation mechanism within engineered barrier was defined and its influence on safety was evaluated. We made probabilistic safety assessment by obtaining the probability distribution functions of important input variables and also made a sensitivity analysis. The maximum annual dose rate was shown to be below the safety limit value of 10 mSv/yr. The structure and element of safety case was developed to increase reliability of safety assessment methodology for a deep geological repository. Finally, milestone for safety case development and implementation strategy for each safety case element was also proposed

  6. The Integrated Safety Management System (ISMS) of the US Department of Energy

    International Nuclear Information System (INIS)

    Linn, M.A.

    1999-01-01

    While the Integrated Safety Management System (ISMS) program is a fairly rational approach to safety, it represents the culmination of several years of hard-earned lessons learned. Considering the size and the diversity of interrelated elements which make up the USDOE complex, this result shows the determination of both the USDOE and its contractors to bring safety hazards to heel. While these lessons learned were frustrating and expensive, the results were several key insights upon which the ISMS was built: (1) Ensure safety management is integral to the business. Safety management must become part of each work activity, rather that something in addition to or on top of. (2) Tailor the safety requirements to the work and its hazards. In order to be cost-effective and efficient, safety management should have flexibility in order to match safety requirements with the level of the hazards in a graded manner. (3) Safety management must be coherent and integrated. Large and complex organizations are no excuse for fragmented and overlapping safety initiatives and programs. Simple, from the ground up objectives and principles must be defined and used to guide a comprehensive safety management program. (4) A safety management system must balance resources and priorities. The system must provide the means to balance resources against the particular work hazards, recognizing that different degrees of hazards requires corresponding prevention measures. (5) Clear roles and responsibilities for safety management must be defined. Both the regulator and the contractor have specific responsibilities for safety which must be clearly articulated at all levels of the work processes. (6) Those responsible for safety must have the competence to carry it out. Those assigned responsibilities must have the experience, knowledge, skills, and authority to carry them out. As one can surmise, the ISMS is not a new program to be implemented, but rather a new attitude which must be adopted

  7. Integral urban project and safety. Building barriers or bridges?

    CSIR Research Space (South Africa)

    Landman, K

    2006-03-01

    Full Text Available Planning and design measures can be utilised successfully to enhance feelings of safety in areas where people feel vulnerable. The study of the relationship between crime and the physical environment has resulted in various theoretical approaches...

  8. Safety First! The topic of safety in reversed integration of people with intellectual disabilities.

    NARCIS (Netherlands)

    Venema, Eleonora; Vlaskamp, Carla; Otten, Sabine

    2017-01-01

    Background: Physical integration is believed to be a precondition for social integration. One might expect that in so-called reversed integration, where people without intellectual disabilities (ID) actively choose to live next to people with ID, conditions for physical integration are more optimal,

  9. The Conceptual Framework for Ensuring Economic Safety of Corporate Integration Processes

    Directory of Open Access Journals (Sweden)

    Gutsaliuk Oleksii M.

    2016-08-01

    Full Text Available The objective growth of the number of displays and influence of negative factors of threats from the environment actualizes the issue of ensuring economic safety of national economic entities. The article notes that simultaneously with counteracting threats enterprises are working for development, one form of which is the establishment of corporate structures and implementation of integration processes. It is proposed to ensure achieving the desired level of the corporate structure economic safety through optimizing the correlation of resources and competencies, skills and technologies for their use within the integrated logistics value chain. In this case it is the implementation of the integration process that serves as an instrument for achieving this optimal correlation, and the level of economic safety is considered as one of the optimization criteria. The system of authors’ hypotheses is taken as the basis for ensuring economic safety of the corporate integration process. Each of the hypotheses corresponds to a set of conceptual principles aimed at practical implementation of the proposed approaches. Within these conceptual principles the relationship between incentives and benefits of integration and the basis for ensuring their safety is presented, the differences between safety of functioning and safety of development are studied, the use of the methodology of logistics to harmonize the interests of participants of the corporate structure is justified, the relevance of applying the resource approach to manage the integration and development safety is proved. The graphical representation of causal relationships between the proposed conceptual principles allowed formalizing the subject area of studying corporate integration safety

  10. Integral Safety Assessment of Underground Storage of CO2 in Barendrecht, the Netherlands

    International Nuclear Information System (INIS)

    Vijgen, L.; Nitert, M.; Buijtendijk, B.; Van Dalen, A.

    2009-10-01

    The DCMR Environmental Protection Agency Rijnmond in the Netherlands conducted an Integral Safety Assessment of Underground Storage of CO2 in Barendrecht, the Netherlands, in cooperation with the involved safety and supervision authorities. The following aspects of the entire storage project and its safety issues have been examined: the compressor station in Pernis; the underground pipes between the compressor station and the injection locations; and the injection locations Barendrecht-Ziedewij and Barendrecht. [nl

  11. Integration of Behaviour-Based Safety Programme into Engineering Laboratories and Workshops Conceptually

    Science.gov (United States)

    Koo, Kean Eng; Zain, Ahmad Nurulazam Md; Zainal, Siti Rohaida Mohamed

    2012-01-01

    The purpose of this conceptual research framework is to develop and integrate a safety training model using a behaviour-based safety training programme into laboratories for young adults, during their tertiary education, particularly in technical and vocational education. Hence, this research will be investigating the outcome of basic safety…

  12. Integrated Safety and Security Risk Assessment Methods: A Survey of Key Characteristics and Applications

    NARCIS (Netherlands)

    Chockalingam, Sabarathinam; Hadziosmanovic, D.; Pieters, Wolter; Texeira, Andre; van Gelder, Pieter

    2016-01-01

    Over the last years, we have seen several security incidents that compromised system safety, of which some caused physical harm to people. Meanwhile, various risk assessment methods have been developed that integrate safety and security, and these could help to address the corresponding threats by

  13. Integrated care: an Information Model for Patient Safety and Vigilance Reporting Systems.

    Science.gov (United States)

    Rodrigues, Jean-Marie; Schulz, Stefan; Souvignet, Julien

    2015-01-01

    Quality management information systems for safety as a whole or for specific vigilances share the same information types but are not interoperable. An international initiative tries to develop an integrated information model for patient safety and vigilance reporting to support a global approach of heath care quality.

  14. Integrated occupational safety and health management solutions and industrial cases

    CERN Document Server

    Häkkinen, Kari; Niskanen, Toivo

    2015-01-01

    Maximizing reader insights into a new movement toward leadership approaches that are collaborated and shared,  and which views Occupational Safety and Health (OSH) and performance excellence within the wider examination of leadership relationships and practices, this book argues that these relationships and processes are so central to the establishment of OSH functioning that studying them warrants a broad, cross-disciplinary, multiple method analysis. Exploring the complexity of leadership by the impact that contexts (e.g., national and organizational culture) may have on leaders, this book discusses the related literature, then moves forward to show how a more comprehensive practical approach to Occupational Safety and Health and performance excellence can function on levels pertaining to events, individuals, groups, and organizations. This book proposes that greater clarity in understanding leadership in Occupational Safety and Health and performance excellence can be developed from addressing two fundame...

  15. Integration of Safety in the Building Delivery System

    DEFF Research Database (Denmark)

    Jørgensen, Kirsten; Sander, Dag; Staghøj, Aage

    2010-01-01

    become a natural part of the construction process and thereby also have them incorporated into the detailed design process. The practical value of the concept depends on how you manage and organise the detailed design process. Keeping health and safety at work in mind through all phases...... of a building assignment, then it becomes much easier to organise the construction site in a safety wise responsible way. In Denmark a report has been drawn up which illustrates how this could be done. The method for implementing this illustration is based on the lean construction model, which is the method...

  16. DARHT: INTEGRATION OF AUTHORIZATION BASIS REQUIREMENTS AND WORKER SAFETY

    International Nuclear Information System (INIS)

    MC CLURE, D. A.; NELSON, C. A.; BOUDRIE, R. L.

    2001-01-01

    This document describes the results of consensus agreements reached by the DARHT Safety Planning Team during the development of the update of the DARHT Safety Analysis Document (SAD). The SAD is one of the Authorization Basis (AB) Documents required by the Department prior to granting approval to operate the DARHT Facility. The DARHT Safety Planning Team is lead by Mr. Joel A. Baca of the Department of Energy Albuquerque Operations Office (DOE/AL). Team membership is drawn from the Department of Energy Albuquerque Operations Office, the Department of Energy Los Alamos Area Office (DOE/LAAO), and several divisions of the Los Alamos National Laboratory. Revision 1 of the DARHT SAD had been written as part of the process for gaining approval to operate the Phase 1 (First Axis) Accelerator. Early in the planning stage for the required update of the SAD for the approval to operate both Phase 1 and Phase 2 (First Axis and Second Axis) DARHT Accelerator, it was discovered that a conflict existed between the Laboratory approach to describing the management of facility and worker safety

  17. Mainstreaming road safety in the regional integration of the East ...

    African Journals Online (AJOL)

    The East African Community (EAC) comprising of five states: Burundi, Kenya, Rwanda, Tanzania and Uganda bear a disproportionate burden of the global public health burden for road traffic injuries (RTIs). In response to this, each state has devised its own road safety measures, but not at the EAC level. This paper aims to ...

  18. Towards an integrated approach in supporting microbiological food safety decisions

    NARCIS (Netherlands)

    Havelaar, A.H.; Bräunig, J.; Christiansen, K.; Cornu, M.; Hald, T.; Mangen, M.J.J.; Molbak, K.; Pielaat, A.; Snary, E.; Pelt, van W.; Velthuis, A.G.J.; Wahlström, H.

    2007-01-01

    Decisions on food safety involve consideration of a wide range of concerns including the public health impact of foodborne illness, the economic importance of the agricultural sector and the food industry, and the effectiveness and efficiency of interventions. To support such decisions, we propose

  19. Integrated vehicle's lateral safety: the LATERAL SAFE experience

    NARCIS (Netherlands)

    Amditis, A.; Floudas, N.; Kaiser-Dieckhoff, U.; Hackbarth, T.; Broek, S.P. van den; Miglietta, M.; Danielson, L.; Gemou, M.; Bekiaris, E.

    2008-01-01

    The applications developed and the evaluation results of the EU funded automotive safety PReVENT IP subproject LATERAL SAFE are described. The data synthesis algorithms that aim at achieving a reliable representation of the objects and their kinematics, in the lateral and rear fields of the host

  20. Integrated vehicle’s lateral safety: the LATERAL SAFE experience

    NARCIS (Netherlands)

    Amditis, A.; Floudas, N.; Kaiser-Dieckhoff, U.; Hackbarth, T.; Broek, S.P. van den; Miglietta, M.; Danielson, L.; Gemou, M.; Bekiaris, E.

    2008-01-01

    The applications developed and the evaluation results of the EU funded automotive safety PReVENT IP subproject LATERAL SAFE are described. The data synthesis algorithms that aim at achieving a reliable representation of the objects and their kinematics, in the lateral and rear fields of the host

  1. From extended integrity monitoring to the safety evaluation of satellite-based localisation system

    International Nuclear Information System (INIS)

    Legrand, Cyril; Beugin, Julie; Marais, Juliette; Conrard, Blaise; El-Koursi, El-Miloudi; Berbineau, Marion

    2016-01-01

    Global Navigation Satellite Systems (GNSS) such as GPS, already used in aeronautics for safety-related applications, can play a major role in railway safety by allowing a train to locate itself safely. However, in order to implement this positioning solution in any embedded system, its performances must be evaluated according to railway standards. The evaluation of GNSS performances is not based on the same attributes class than RAMS evaluation. Face to these diffculties, we propose to express the integrity attribute, performance of satellite-based localisation. This attribute comes from aeronautical standards and for a hybridised GNSS with inertial system. To achieve this objective, the integrity attribute must be extended to this kind of system and algorithms initially devoted to GNSS integrity monitoring only must be adapted. Thereafter, the formalisation of this integrity attribute permits us to analyse the safety quantitatively through the probabilities of integrity risk and wrong-side failure. In this paper, after an introductory discussion about the use of localisation systems in railway safety context together with integrity issues, a particular integrity monitoring is proposed and described. The detection events of this algorithm permit us to conclude about safety level of satellite-based localisation system.

  2. Registration of vehicle based panoramic image and LiDAR point cloud

    Science.gov (United States)

    Chen, Changjun; Cao, Liang; Xie, Hong; Zhuo, Xiangyu

    2013-10-01

    Higher quality surface information would be got when data from optical images and LiDAR were integrated, owing to the fact that optical images and LiDAR point cloud have unique characteristics that make them preferable in many applications. While most previous works focus on registration of pinhole perspective cameras to 2D or 3D LiDAR data. In this paper, a method for the registration of vehicle based panoramic image and LiDAR point cloud is proposed. Using the translation among panoramic image, single CCD image, laser scanner and Position and Orientation System (POS) along with the GPS/IMU data, precise co-registration between the panoramic image and the LiDAR point cloud in the world system is achieved. Results are presented under a real world data set collected by a new developed Mobile Mapping System (MMS) integrated with a high resolution panoramic camera, two laser scanners and a POS.

  3. Estimation of average hazardous-event-frequency for allocation of safety-integrity levels

    International Nuclear Information System (INIS)

    Misumi, Y.; Sato, Y.

    1999-01-01

    One of the fundamental concepts of the draft international standard, IEC 61508, is target failure measures to be allocated to Electric/Electronic/Programmable Electronic Safety-Related Systems, i.e. Safety Integrity Levels. The Safety Integrity Levels consist of four discrete probabilistic levels for specifying the safety integrity requirements or the safety functions to be allocated to Electric/Electronic/Programmable Electronic Safety-Related Systems. In order to select the Safety Integrity Levels the draft standard classifies Electric/Electronic/Programmable Electronic Safety-Related Systems into two modes of operation using demand frequencies only. It is not clear which modes of operation should be applied to Electric/Electronic/Programmable Electronic Safety-Related Systems taking into account the demand-state probability and the spurious demand frequency. It is essential for the allocation of Safety Integrity Levels that generic algorithms be derived by involving possible parameters, which make it possible to model the actuality of real systems. The present paper addresses this issue. First of all, the overall system including Electric/Electronic/programmable Electronic Safety-Related Systems is described using a simplified fault-tree. Then, the relationships among demands, demand-states and proof-tests are studied. Overall systems are classified into two groups: a non-demand-state-at-proof-test system which includes both repairable and non-repairable demand states and a constant-demand-frequency system. The new ideas such as a demand-state, spurious demand-state, mean time between detections, rates of d-failure and h-failure, and an h/d ratio are introduced in order to make the Safety Integrity Levels and modes of operation generic and comprehensive. Finally, the overall system is simplified and modeled by fault-trees using Priority-AND gates. At the same time the assumptions for modeling are described. Generic algorithms to estimate hazardous

  4. Integrating RAMS engineering and management with the safety life cycle of IEC 61508

    International Nuclear Information System (INIS)

    Lundteigen, Mary Ann; Rausand, Marvin; Utne, Ingrid Bouwer

    2009-01-01

    This article outlines a new approach to reliability, availability, maintainability, and safety (RAMS) engineering and management. The new approach covers all phases of the new product development process and is aimed at producers of complex products like safety instrumented systems (SIS). The article discusses main RAMS requirements to a SIS and presents these requirements in a holistic perspective. The approach is based on a new life cycle model for product development and integrates this model into the safety life cycle of IEC 61508. A high integrity pressure protection system (HIPPS) for an offshore oil and gas application is used to illustrate the approach.

  5. Environment, safety, and health information technology systems integration.

    Energy Technology Data Exchange (ETDEWEB)

    Hendrickson, David A.; Bayer, Gregory W.

    2006-02-01

    The ES&H Information Systems department, motivated by the numerous isolated information technology systems under its control, undertook a significant integration effort. This effort was planned and executed over the course of several years and parts of it still continue today. The effect was to help move the ES&H Information Systems department toward integration with the corporate Information Solutions and Services center.

  6. Nuclear safety, security and safeguards. An application of an integrated approach

    Energy Technology Data Exchange (ETDEWEB)

    Chapman, Howard; Edwards, Jeremy; Fitzpatrick, Joshua; Grundy, Colette; Rodger, Robert; Scott, Jonathan [National Nuclear Laboratory, Warrington (United Kingdom)

    2018-01-15

    National Nuclear Laboratory has recently produced a paper regarding the integrated approach of nuclear safety, security and safeguards. The paper considered the international acknowledgement of the inter-relationships and potential benefits to be gained through improved integration of the nuclear '3S'; Safety, Security and Safeguards. It considered that combining capabilities into one synergistic team can provide improved performance and value. This approach to integration has been adopted, and benefits realised by the National Nuclear Laboratory through creation of a Safety, Security and Safeguards team. In some instances the interface is clear and established, as is the case between safety and security in the areas of Vital Area Identification. In others the interface is developing such as the utilisation of safeguards related techniques such as nuclear material accountancy and control to enhance the security of materials. This paper looks at a practical example of the progress to date in implementing Triple S by a duty holder.

  7. RECENT ADDITIONS OF CRITICALITY SAFETY RELATED INTEGRAL BENCHMARK DATA TO THE ICSBEP AND IRPHEP HANDBOOKS

    Energy Technology Data Exchange (ETDEWEB)

    J. Blair Briggs; Lori Scott; Yolanda Rugama; Enrico Sartori

    2009-09-01

    High-quality integral benchmark experiments have always been a priority for criticality safety. However, interest in integral benchmark data is increasing as efforts to quantify and reduce calculational uncertainties accelerate to meet the demands of future criticality safety needs to support next generation reactor and advanced fuel cycle concepts. The importance of drawing upon existing benchmark data is becoming more apparent because of dwindling availability of critical facilities worldwide and the high cost of performing new experiments. Integral benchmark data from the International Handbook of Evaluated Criticality Safety Benchmark Experiments and the International Handbook of Reactor Physics Benchmark Experiments are widely used. Benchmark data have been added to these two handbooks since the last Nuclear Criticality Safety Division Topical Meeting in Knoxville, Tennessee (September 2005). This paper highlights these additions.

  8. Recent additions of criticality safety related integral benchmark data to the ICSBEP and IRPHEP handbooks

    International Nuclear Information System (INIS)

    Briggs, J. B.; Scott, L.; Rugama, Y.; Sartori, E.

    2009-01-01

    High-quality integral benchmark experiments have always been a priority for criticality safety. However, interest in integral benchmark data is increasing as efforts to quantify and reduce calculational uncertainties accelerate to meet the demands of future criticality safety needs to support next generation reactor and advanced fuel cycle concepts. The importance of drawing upon existing benchmark data is becoming more apparent because of dwindling availability of critical facilities worldwide and the high cost of performing new experiments. Integral benchmark data from the International Handbook of Evaluated Criticality Safety Benchmark Experiments and the International Handbook of Reactor Physics Benchmark Experiments are widely used. Benchmark data have been added to these two handbooks since the last Nuclear Criticality Safety Division Topical Meeting in Knoxville, Tennessee (September 2005). This paper highlights these additions. (authors)

  9. REcent Additions Of Criticality Safety Related Integral Benchmark Data To The Icsbep And Irphep Handbooks

    International Nuclear Information System (INIS)

    Briggs, J. Blair; Scott, Lori; Rugama, Yolanda; Sartori, Enrico

    2009-01-01

    High-quality integral benchmark experiments have always been a priority for criticality safety. However, interest in integral benchmark data is increasing as efforts to quantify and reduce calculational uncertainties accelerate to meet the demands of future criticality safety needs to support next generation reactor and advanced fuel cycle concepts. The importance of drawing upon existing benchmark data is becoming more apparent because of dwindling availability of critical facilities worldwide and the high cost of performing new experiments. Integral benchmark data from the International Handbook of Evaluated Criticality Safety Benchmark Experiments and the International Handbook of Reactor Physics Benchmark Experiments are widely used. Benchmark data have been added to these two handbooks since the last Nuclear Criticality Safety Division Topical Meeting in Knoxville, Tennessee (September 2005). This paper highlights these additions.

  10. Occupational Therapy and Sensory Integration for Children with Autism: A Feasibility, Safety, Acceptability and Fidelity Study

    Science.gov (United States)

    Schaaf, Roseann C.; Benevides, Teal W.; Kelly, Donna; Mailloux-Maggio, Zoe

    2012-01-01

    Objective: To examine the feasibility, safety, and acceptability of a manualized protocol of occupational therapy using sensory integration principles for children with autism. Methods: Ten children diagnosed with autism spectrum disorder ages 4-8 years received intensive occupational therapy intervention using sensory integration principles…

  11. Integration of safety in management tasks in onshore transport SME´s

    DEFF Research Database (Denmark)

    Jørgensen, Kirsten

    2015-01-01

    with animals and the risk of violence and robbery. To create a high level of safety in an enterprise is a difficult task that demands a great degree of management engagement. It is not only a question of having the right equipment, procedures and organization etc.; it is also necessary for everyone...... in the enterprise to have an understanding of safety and feel obligated to take responsibility for safety in all work at all times. Accident research shows that safety must be integrated in the whole enterprise and function on all levels of management, while it must also involve all employees in their daily work...... prevention. The result is a realistic strategy for integration safety, quality and environmental factors in an SME and procedures for how to go from strategy to action. Different tools were developed to fulfil the strategy ranging from risk identification, involvement of the employee and motivational...

  12. Integrating scientific results for a post-closure safety demonstration

    International Nuclear Information System (INIS)

    Taylor, E.C.; Ramspott, L.D.; Sinnock, S.; Sprecher, W.M.

    1994-01-01

    The U.S. Department of Energy (DOE) is developing a nuclear waste management system that will accept high-level radioactive waste, transport it, store it, and ultimately emplace it in a deep geologic repository. The key activity now is determining whether Yucca Mountain, Nevada is suitable as a site for the repository. If so, the crucial technological advance will be the demonstration that disposal of nuclear waste will be safe for thousands of years after closure. Recent regulatory, legal, and scientific developments imply that the safety demonstration must be simple. The scientific developments taken together support a simple set of hypotheses that constitute a post-closure safety argument for a repository at Yucca Mountain. If the understanding of Yucca Mountain hydrology presented in the Site Characterization Plan proves correct, then these hypotheses might be confirmed by combining results of Surface-Based Testing with early testing results in the Exploratory Studies Facility

  13. Quality and safety is the integral part of our business

    International Nuclear Information System (INIS)

    Fadeev, Y.

    2011-01-01

    During 65 years from Joint-stock Company Afrikantov OKBM foundation over 400 reactor projects were developed - primarily, various modifications of marine propulsion reactors for nuclear submarines and icebreakers of several generations. Today, OKBM designs reactors of various types and purposes as well as equipment, control and protection mechanisms, and is the world leader in fast-neutron sodium-cooled reactor technology. Much attention in OKBM is given to the safety and quality of production, specialists education [ru

  14. Integrated safety assessment report: Integrated Safety Assessment Program: Millstone Nuclear Power Station, Unit 1 (Docket No. 50-245): Draft report

    International Nuclear Information System (INIS)

    1987-04-01

    The Integrated Safety Assessment Program (ISAP) was initiated in November 1984, by the US Nuclear Regulatory Commission to conduct integrated assessments for operating nuclear power reactors. The integrated assessment is conducted in a plant-specific basis to evaluate all licensing actions, licensee initiated plant improvements and selected unresolved generic/safety issues to establish implementation schedules for each item. In addition, procedures will be established to allow for a periodic updating of the schedules to account for licensing issues that arise in the future. This report documents the review of Millstone Nuclear Power Station, Unit No. 1, operated by Northeast Nuclear Energy Company (located in Waterford, Connecticut). Millstone Nuclear Power Station, Unit No. 1, is one of two plants being reviewed under the pilot program for ISAP. This report indicates how 85 topics selected for review were addressed. This report presents the staff's recommendations regarding the corrective actions to resolve the 85 topics and other actions to enhance plant safety. The report is being issued in draft form to obtain comments from the licensee, nuclear safety experts, and the Advisory Committee for Reactor Safeguards (ACRS). Once those comments have been resolved, the staff will present its positions, along with a long-term implementation schedule from the licensee, in the final version of this report

  15. Idaho National Laboratory Integrated Safety Management System 2010 Effectiveness Review and Declaration Report

    Energy Technology Data Exchange (ETDEWEB)

    Thomas J. Haney

    2010-12-01

    Idaho National Laboratory completes an annual Integrated Safety Management System effectiveness review per 48 CFR 970.5223-1 “Integration of Environment, Safety and Health into Work Planning and Execution.” The annual review assesses ISMS effectiveness, provides feedback to maintain system integrity, and helps identify target areas for focused improvements and assessments for the following year. Using one of the three Department of Energy (DOE) descriptors in DOE M 450.4-1 regarding the state of ISMS effectiveness during Fiscal Year (FY) 2010, the information presented in this review shows that INL achieved “Effective Performance.”

  16. Integration of safety culture in transient analyses for nuclear power plants

    International Nuclear Information System (INIS)

    Stosic, Zoran V.; Stoll, Uwe

    2009-01-01

    In the nuclear field Safety Culture is the arrangement of attitudes and characteristics in individuals and organisations which determines first and foremost that nuclear power plant safety issues receive adequate attention due to their outstanding significance. It differs from general Corporate Culture via its concept of core hazards and the potentially large effects associated with the release of radioactivity. One can talk about positive and negative Safety Cultures. A positive Safety Culture assumes that the whole is more than the sum of the parts. The different parts interact to increase the overall effectiveness. In a negative Safety Culture the opposite is the case, with the action of some individuals restricted by the cynicism of others. Some examples of issues that contribute to a negative safety culture are: non-adherence to the established instructions and procedures, unclear definition of responsibilities, disinterest and inattentiveness, overestimation of own capabilities and arrogance, unclear rules, and mistrust between involved organisations. In addition to differentiation and importance of Safety Culture, necessary commitment levels, safety management framework, the paper discusses integration of Safety Culture in transient analyses of nuclear power plants. In this course the commitment to Safety Culture is defined as: a good Safety Culture depends on the continuous commitment and fulfilment of all involved organizations, persons and processes without any exception. (author)

  17. Idaho National Laboratory Integrated Safety Management System 2011 Effectiveness Review and Declaration Report

    Energy Technology Data Exchange (ETDEWEB)

    Farren Hunt

    2011-12-01

    Idaho National Laboratory (INL) performed an annual Integrated Safety Management System (ISMS) effectiveness review per 48 Code of Federal Regulations (CFR) 970.5223-1, 'Integration of Environment, Safety and Health into Work Planning and Execution.' The annual review assessed Integrated Safety Management (ISM) effectiveness, provided feedback to maintain system integrity, and helped identify target areas for focused improvements and assessments for fiscal year (FY) 2012. The information presented in this review of FY 2011 shows that the INL has performed many corrective actions and improvement activities, which are starting to show some of the desired results. These corrective actions and improvement activities will continue to help change culture that will lead to better implementation of defined programs, resulting in moving the Laboratory's performance from the categorization of 'Needs Improvement' to the desired results of 'Effective Performance.'

  18. Integration of safety engineering into a cost optimized development program.

    Science.gov (United States)

    Ball, L. W.

    1972-01-01

    A six-segment management model is presented, each segment of which represents a major area in a new product development program. The first segment of the model covers integration of specialist engineers into 'systems requirement definition' or the system engineering documentation process. The second covers preparation of five basic types of 'development program plans.' The third segment covers integration of system requirements, scheduling, and funding of specialist engineering activities into 'work breakdown structures,' 'cost accounts,' and 'work packages.' The fourth covers 'requirement communication' by line organizations. The fifth covers 'performance measurement' based on work package data. The sixth covers 'baseline requirements achievement tracking.'

  19. Measuring Best Practices for Workplace Safety, Health, and Well-Being: The Workplace Integrated Safety and Health Assessment.

    Science.gov (United States)

    Sorensen, Glorian; Sparer, Emily; Williams, Jessica A R; Gundersen, Daniel; Boden, Leslie I; Dennerlein, Jack T; Hashimoto, Dean; Katz, Jeffrey N; McLellan, Deborah L; Okechukwu, Cassandra A; Pronk, Nicolaas P; Revette, Anna; Wagner, Gregory R

    2018-05-01

    To present a measure of effective workplace organizational policies, programs, and practices that focuses on working conditions and organizational facilitators of worker safety, health and well-being: the workplace integrated safety and health (WISH) assessment. Development of this assessment used an iterative process involving a modified Delphi method, extensive literature reviews, and systematic cognitive testing. The assessment measures six core constructs identified as central to best practices for protecting and promoting worker safety, health and well-being: leadership commitment; participation; policies, programs, and practices that foster supportive working conditions; comprehensive and collaborative strategies; adherence to federal and state regulations and ethical norms; and data-driven change. The WISH Assessment holds promise as a tool that may inform organizational priority setting and guide research around causal pathways influencing implementation and outcomes related to these approaches.

  20. Integration of radiation protection in safety management: sharing best practices between radiation protection and other safety areas

    International Nuclear Information System (INIS)

    Kockerols, Pierre; Fessler, Andreas

    2008-01-01

    Full text: The Institute for Reference Materials and Measurements (IRMM) located in Geel is one of the seven institutes of the Joint Research Centre of the European Commission (EC, DG JRC). The institute was founded in 1960 as a nuclear research centre, but has gradually shifted its activities to also include 'non-nuclear' domains, mainly in the areas of food safety and environmental surveillance. As the activities on the IRMM site are currently quite diversified, they necessitate the operation of nuclear controlled areas, accelerators, as well as bio safety restricted areas and chemical laboratories. Therefore, the care for occupational health and safety and for environmental protection has to take into consideration various types of hazards and threats. Recently an integrated management system according to ISO-9001, ISO-14001 and OHSAS-18001 was implemented. The integrated system combines 'vertically' quality, occupational health and safety and environmental issues and covers 'horizontally' the nuclear, biological and chemical fields. The paper outlines how the radiation protection can be included in an overall health, safety and environmental management system. It will give various practical examples where synergies can be applied: 1-) the overall policy; 2-) The assessment and ranking of all risks and the identification, in a combined way, of the appropriate prevention measures; 3-) The planning and review of related actions; 4-) The monitoring, auditing and registration of anomalies and incidents and the definition of corrective actions; 5-) The training of personnel based on lessons learned from past experiences; 6-) The organisation of an internal emergency plan dealing with nuclear and non-nuclear hazards. Based on these examples, the benefits of having an integrated approach are commented. In addition, the paper will illustrate how the recent ICRP fundamental recommendations and more particularly some of the principles of radiation protection such as

  1. 48 CFR 970.5223-1 - Integration of environment, safety, and health into work planning and execution.

    Science.gov (United States)

    2010-10-01

    ..., safety, and health into work planning and execution. 970.5223-1 Section 970.5223-1 Federal Acquisition... Integration of environment, safety, and health into work planning and execution. As prescribed in 970.2303-3(b), insert the following clause: Integration of Environment, Safety, and Health Into Work Planning and...

  2. Integrating safety and health during deactiviation: With lessons learned from PUREX

    International Nuclear Information System (INIS)

    1995-01-01

    This report summarizes an integrated safety and health approach used during facility deactivation activities at the Department of Energy (DOE) Plutonium-Uranium Extraction (PUREX) Facility in Hanford, Washington. Resulting safety and health improvements and the potential, complex-wide application of this approach are discussed in this report through a description of its components and the impacts, or lessons-learned, of its use during the PUREX deactivation project. As a means of developing and implementing the integrated safety and health approach, the PUREX technical partnership was established in 1993 among the Office of Environment, Safety and Health's Office of Worker Health and Safety (EH-5); the Office of Environmental Management's Offices of Nuclear Material and Facility Stabilization (EM-60) and Compliance and Program Coordination (EM-20); the DOE Richland Operations Office; and the Westinghouse Hanford Company. It is believed that this report will provide guidance for instituting an integrated safety and health approach not only for deactivation activities, but for decommissioning and other clean-up activities as well. This confidence is based largely upon the rationality of the approach, often termed as common sense, and the measurable safety and health and project performance results that application of the approach produced during actual deactivation work at the PUREX Facility

  3. Integrating Safety and Mission Assurance into Systems Engineering Modeling Practices

    Science.gov (United States)

    Beckman, Sean; Darpel, Scott

    2015-01-01

    During the early development of products, flight, or experimental hardware, emphasis is often given to the identification of technical requirements, utilizing such tools as use case and activity diagrams. Designers and project teams focus on understanding physical and performance demands and challenges. It is typically only later, during the evaluation of preliminary designs that a first pass, if performed, is made to determine the process, safety, and mission quality assurance requirements. Evaluation early in the life cycle, though, can yield requirements that force a fundamental change in design. This paper discusses an alternate paradigm for using the concepts of use case or activity diagrams to identify safety hazard and mission quality assurance risks and concerns using the same systems engineering modeling tools being used to identify technical requirements. It contains two examples of how this process might be used in the development of a space flight experiment, and the design of a Human Powered Pizza Delivery Vehicle, along with the potential benefits to decrease development time, and provide stronger budget estimates.

  4. Idaho National Laboratory Integrated Safety Management System FY 2012 Effectiveness Review and Declaration Report

    Energy Technology Data Exchange (ETDEWEB)

    Farren Hunt

    2012-12-01

    Idaho National Laboratory (INL) performed an Annual Effectiveness Review of the Integrated Safety Management System (ISMS), per 48 Code of Federal Regulations (CFR) 970.5223 1, “Integration of Environment, Safety and Health into Work Planning and Execution.” The annual review assessed Integrated Safety Management (ISM) effectiveness, provided feedback to maintain system integrity, and identified target areas for focused improvements and assessments for fiscal year (FY) 2013. Results of the FY 2012 annual effectiveness review demonstrated that the INL’s ISMS program was significantly strengthened. Actions implemented by the INL demonstrate that the overall Integrated Safety Management System is sound and ensures safe and successful performance of work while protecting workers, the public, and environment. This report also provides several opportunities for improvement that will help further strengthen the ISM Program and the pursuit of safety excellence. Demonstrated leadership and commitment, continued surveillance, and dedicated resources have been instrumental in maturing a sound ISMS program. Based upon interviews with personnel, reviews of assurance activities, and analysis of ISMS process implementation, this effectiveness review concludes that ISM is institutionalized and is “Effective”.

  5. [Innovative training for enhancing patient safety. Safety culture and integrated concepts].

    Science.gov (United States)

    Rall, M; Schaedle, B; Zieger, J; Naef, W; Weinlich, M

    2002-11-01

    Patient safety is determined by the performance safety of the medical team. Errors in medicine are amongst the leading causes of death of hospitalized patients. These numbers call for action. Backgrounds, methods and new forms of training are introduced in this article. Concepts from safety research are transformed to the field of emergency medical treatment. Strategies from realistic patient simulator training sessions and innovative training concepts are discussed. The reasons for the high numbers of errors in medicine are not due to a lack of medical knowledge, but due to human factors and organisational circumstances. A first step towards an improved patient safety is to accept this. We always need to be prepared that errors will occur. A next step would be to separate "error" from guilt (culture of blame) allowing for a real analysis of accidents and establishment of meaningful incident reporting systems. Concepts with a good success record from aviation like "crew resource management" (CRM) training have been adapted my medicine and are ready to use. These concepts require theoretical education as well as practical training. Innovative team training sessions using realistic patient simulator systems with video taping (for self reflexion) and interactive debriefing following the sessions are very promising. As the need to reduce error rates in medicine is very high and the reasons, methods and training concepts are known, we are urged to implement these new training concepts widely and consequently. To err is human - not to counteract it is not.

  6. Integrated prevention: new perspectives for public safety policies in Brazil

    Directory of Open Access Journals (Sweden)

    Rodrigo Ghiringhelli de Azevedo

    2006-04-01

    Full Text Available This article seeks to identify the elements that are establishing a new perspective in the handling contemporary social conflicts. It is based on the recognition of the limits of the reactive paradigm, characteristic of modernity in relation to criminal issues, which is based on the formal and dogmatic logic of government normativity. On one hand the crisis in this paradigm has led to the reappearance of a punitive approach, and proposals to increase punishments that are no longer seen as a retribution for a crime or a way to reinsert the individual into society. Punishments have often become mechanisms of pure and simple contention and suppression of rights in name of efficiency and combating crime. On the other hand, many experiences are appearing in public safety administration based on citizen participation, and on the engagement of civil society in policies for social inclusion and public control of police activity and of the penal system.

  7. An integrated risk sensing system for geo-structural safety

    Institute of Scientific and Technical Information of China (English)

    H.W. Huang; D.M. Zhang; B.M. Ayyub

    2017-01-01

    Over the last decades, geo-structures are experiencing a rapid development in China. The potential risks inherent in the huge amount of construction and asset operation projects in China were well managed in the major project, i.e. the project of Shanghai Yangtze tunnel in 2002. Since then, risk assessment of geo-structures has been gradually developed from a qualitative manner to a quantitative manner. However, the current practices of risk management have been paid considerable attention to the assessment, but little on risk control. As a result, the responses to risks occurrences after a comprehensive assessment are basically too late. In this paper, a smart system for risk sensing incorporating the wireless sensor network (WSN) on-site visualization techniques and the resilience-based repair strategy was proposed. The merit of this system is the real-time monitoring for geo-structural performance and dynamic pre-warning for safety of on-site workers. The sectional convergence, joint opening, and seepage of segmental lining of shield tunnel were monitored by the micro-electro-mechanical systems (MEMS) based sensors. The light emitting diode (LED) coupling with the above WSN system was used to indicate different risk levels on site. By sensing the risks and telling the risks in real time, the geo-risks could be controlled and the safety of geo-structures could be assured to a certain degree. Finally, a resilience-based analysis model was proposed for designing the repair strategy by using the measured data from the WSN system. The application and efficiency of this system have been validated by two cases including Shanghai metro tunnel and underwater road tunnel.

  8. Integrated Plant Safety Assessment, Systematic Evaluation Program: Yankee Nuclear Power Station (Docket No. 50-29)

    International Nuclear Information System (INIS)

    1987-10-01

    The US Nuclear Regulatory Commission (NRC) has prepared Supplement 1 to the final Integrated Plant Safety Assessment Report (IPSAR) (NUREG-0825), under the scope of the Systematic Evaluation Program (SEP), for Yankee Atomic Electric Company's Yankee Nuclear Power Station located in Rowe, Massachusetts. The SEP was initiated by the NRC to review the design of older operating nuclear power plants to reconfirm and document their safety. This report documents the review completed under the SEP for those issues that required refined engineering evaluations or the continuation of ongoing evaluations after the Final IPSAR for the Yankee plant was issued. The review has provided for (1) an assessment of the significance of differences between current technical positions on selected safety issues and those that existed when Yankee was licensed, (2) a basis for deciding how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. 2 tabs

  9. Fluor Hanford Integrated Safety Management System Phase II Verification Vol 1 & Vol 2

    Energy Technology Data Exchange (ETDEWEB)

    PARSONS, J.E.

    2000-07-15

    The U.S. Department of Energy (DOE) is committed to conducting work efficiently and in a manner that ensures protection of the workers, public, and environment. DOE policy mandates that safety management systems be used to systematically integrate safety into management and work practices at all levels while accomplishing mission goals in an effective and efficient manner. The purpose of the Fluor Hanford (FH) Integrated Safety Management System (ISMS) verification was to determine whether FH's ISM system and processes are sufficiently implemented to accomplish the goal of ''Do work safely.'' The purpose of the DOE, Richland Operations Office (RL) verification was to determine whether RL has established processes that adequately describe RL's role in safety management and if those processes are sufficiently implemented.

  10. Fluor Hanford Integrated Safety Management System Phase II Verification Vol 1 and Vol 2

    CERN Document Server

    Parsons, J E

    2000-01-01

    The U.S. Department of Energy (DOE) is committed to conducting work efficiently and in a manner that ensures protection of the workers, public, and environment. DOE policy mandates that safety management systems be used to systematically integrate safety into management and work practices at all levels while accomplishing mission goals in an effective and efficient manner. The purpose of the Fluor Hanford (FH) Integrated Safety Management System (ISMS) verification was to determine whether FH's ISM system and processes are sufficiently implemented to accomplish the goal of ''Do work safely.'' The purpose of the DOE, Richland Operations Office (RL) verification was to determine whether RL has established processes that adequately describe RL's role in safety management and if those processes are sufficiently implemented.

  11. Fluor Hanford Integrated Safety Management System Phase II Verification Vol 1 and Vol 2

    International Nuclear Information System (INIS)

    PARSONS, J.E.

    2000-01-01

    The U.S. Department of Energy (DOE) is committed to conducting work efficiently and in a manner that ensures protection of the workers, public, and environment. DOE policy mandates that safety management systems be used to systematically integrate safety into management and work practices at all levels while accomplishing mission goals in an effective and efficient manner. The purpose of the Fluor Hanford (FH) Integrated Safety Management System (ISMS) verification was to determine whether FH's ISM system and processes are sufficiently implemented to accomplish the goal of ''Do work safely.'' The purpose of the DOE, Richland Operations Office (RL) verification was to determine whether RL has established processes that adequately describe RL's role in safety management and if those processes are sufficiently implemented

  12. System Interface for an Integrated Intelligent Safety System (ISS for Vehicle Applications

    Directory of Open Access Journals (Sweden)

    Mahammad A. Hannan

    2010-01-01

    Full Text Available This paper deals with the interface-relevant activity of a vehicle integrated intelligent safety system (ISS that includes an airbag deployment decision system (ADDS and a tire pressure monitoring system (TPMS. A program is developed in LabWindows/CVI, using C for prototype implementation. The prototype is primarily concerned with the interconnection between hardware objects such as a load cell, web camera, accelerometer, TPM tire module and receiver module, DAQ card, CPU card and a touch screen. Several safety subsystems, including image processing, weight sensing and crash detection systems, are integrated, and their outputs are combined to yield intelligent decisions regarding airbag deployment. The integrated safety system also monitors tire pressure and temperature. Testing and experimentation with this ISS suggests that the system is unique, robust, intelligent, and appropriate for in-vehicle applications.

  13. Safety measures for integrity test apparatus for IS process. Sulfuric acid decomposition section

    International Nuclear Information System (INIS)

    Noguchi, Hiroki; Kubo, Shinji; Iwatsuki, Jin; Onuki, Kaoru

    2013-07-01

    Hazardous substances such as sulfuric acid, sulfur dioxide and hydrogen iodide acid are employed in thermochemical Iodine-Sulfur (IS) process. It is necessary to take safety measure against workers and external environments to study experimentally on IS process. Presently we have been conducting to verify the soundness of main components made of engineering material in actual corrosive condition. An integrity test apparatus for the components of sulfuric acid decomposition was set up. We will use the hazardous substances such as sulfuric acid and sulfur dioxide and perform the experiment in pressurized condition in this integrity test. Safety measures for the test apparatus, operation and abnormal situation were considered prior to starting the test. This report summarized the consideration results for the safety measures on the integrity test apparatus for the components of sulfuric acid decomposition. (author)

  14. Road identification for its-integrated systems of automotive active safety

    Directory of Open Access Journals (Sweden)

    V. Ivanov

    2005-04-01

    Full Text Available The paper discusses several aspects of active safety control for automotive application. Particular emphasis is placed on the fuzzy logic determination of friction properties of a tyre-road contact. An example of vehicle control systems equipped with off-board sensors of road roughness, temperature, moisture and rain intensity demonstrates the implementation of this approach. The paper proposes conceptual solutions for preventive active safety control applied to vehicles which are integrated in an intelligent transportation system.

  15. Integrated Safety and Security Risk Assessment Methods: A Survey of Key Characteristics and Applications

    OpenAIRE

    Chockalingam, Sabarathinam; Hadziosmanovic, Dina; Pieters, Wolter; Teixeira, Andre; van Gelder, Pieter

    2017-01-01

    Over the last years, we have seen several security incidents that compromised system safety, of which some caused physical harm to people. Meanwhile, various risk assessment methods have been developed that integrate safety and security, and these could help to address the corresponding threats by implementing suitable risk treatment plans. However, an overarching overview of these methods, systematizing the characteristics of such methods, is missing. In this paper, we conduct a systematic l...

  16. ESTIMATION OF PROCESSES REALIZATION RISK AS A MANNER OF SAFETY MANAGEMENT IN THE INTEGRATED SYSTEMS

    Directory of Open Access Journals (Sweden)

    Tatiana Karkoszka

    2011-12-01

    Full Text Available Realization of quality, environmental and occupational health and safety policy using the proposed model of processes' integrated risk estimation leads to the improvement of the analyzed productive processes by the preventive and corrective actions, and in consequence - to their optimization from the point of view of products' quality and in the aspect of quality of environmental influence and occupational health and safety.

  17. ESTIMATION OF PROCESSES REALIZATION RISK AS A MANNER OF SAFETY MANAGEMENT IN THE INTEGRATED SYSTEMS

    Directory of Open Access Journals (Sweden)

    Tatiana Karkoszka

    2011-06-01

    Full Text Available Realization of quality, environmental and occupational health and safety policy using the proposed model of processes' integrated risk estimation leads to the improvement of the analyzed productive processes by the preventive and corrective actions, and in consequence - to their optimization from the point of view of products' quality and in the aspect of quality of environmental influence and occupational health and safety.

  18. Safety features in small integral PWR ABV-6

    Energy Technology Data Exchange (ETDEWEB)

    Baranaev, Youry D. [State Scientific Centre of Russian Federation - Institure for Physics and Power Engineering, Obninsk (Russian Federation)

    1996-04-15

    Long term operation experience of Bilibin Nuclear Power Plant with four EGP-6 reactors of 48MWth each at Chukotka peninsula, as well as results of manifold feasibility studies showed that Small Reactors (SR) have and will have promising market potential in outlying isolated regions of Russia as viable alternative of fossil fuel energy sources. Detailed design and licensing of the Small Floating Nuclear Power Plant Valamin/1/ with two integral pressurized water reactors ABV-6/2, 3/ is under way in Russia. The basic ABV-6 reactor design performance are presented in Table 1.

  19. Towards integrated hygiene and food safety management systems: the Hygieneomic approach.

    Science.gov (United States)

    Armstrong, G D

    1999-09-15

    Integrated hygiene and food safety management systems in food production can give rise to exceptional improvements in food safety performance, but require high level commitment and full functional involvement. A new approach, named hygieneomics, has been developed to assist management in their introduction of hygiene and food safety systems. For an effective introduction, the management systems must be designed to fit with the current generational state of an organisation. There are, broadly speaking, four generational states of an organisation in their approach to food safety. They comprise: (i) rules setting; (ii) ensuring compliance; (iii) individual commitment; (iv) interdependent action. In order to set up an effective integrated hygiene and food safety management system a number of key managerial requirements are necessary. The most important ones are: (a) management systems must integrate the activities of key functions from research and development through to supply chain and all functions need to be involved; (b) there is a critical role for the senior executive, in communicating policy and standards; (c) responsibilities must be clearly defined, and it should be clear that food safety is a line management responsibility not to be delegated to technical or quality personnel; (d) a thorough and effective multi-level audit approach is necessary; (e) key activities in the system are HACCP and risk management, but it is stressed that these are ongoing management activities, not once-off paper generating exercises; and (f) executive management board level review is necessary of audit results, measurements, status and business benefits.

  20. Integrating Safety with Science,Technology and Innovation at Los Alamos National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Rich, Bethany M [Los Alamos National Laboratory

    2012-04-02

    The mission of Los Alamos National Laboratory (LANL) is to develop and apply science, technology and engineering solutions to ensure the safety, security, and reliability of the U.S. nuclear deterrent; reduce global threats; and solve emerging national security challenges. The most important responsibility is to direct and conduct efforts to meet the mission with an emphasis on safety, security, and quality. In this article, LANL Environmental, Safety, and Health (ESH) trainers discuss how their application and use of a kinetic learning module (learn by doing) with a unique fall arrest system is helping to address one the most common industrial safety challenges: slips and falls. A unique integration of Human Performance Improvement (HPI), Behavior Based Safety (BBS) and elements of the Voluntary Protection Program (VPP) combined with an interactive simulator experience is being used to address slip and fall events at Los Alamos.

  1. Integrated approach to knowledge acquisition and safety management of complex plants with emphasis on human factors

    International Nuclear Information System (INIS)

    Kosmowski, K.T.

    1998-01-01

    In this paper an integrated approach to the knowledge acquisition and safety management of complex industrial plants is proposed and outlined. The plant is considered within a man-technology-environment (MTE) system. The knowledge acquisition is aimed at the consequent reliability evaluation of human factor and probabilistic modeling of the plant. Properly structured initial knowledge is updated in life-time of the plant. The data and knowledge concerning the topology of safety related systems and their functions are created in a graphical CAD system and are object oriented. Safety oriented monitoring of the plant includes abnormal situations due to external and internal disturbances, failures of hard/software components and failures of human factor. The operation and safety related evidence is accumulated in special data bases. Data/knowledge bases are designed in such a way to support effectively the reliability and safety management of the plant. (author)

  2. Psychology in nuclear power plants: an integrative approach to safety - general statement

    International Nuclear Information System (INIS)

    Shikiar, R.

    1983-08-01

    Since the accident at the Three Mile Island nuclear power plant on March 28, 1979, the commercial nuclear industry in the United States has paid increasing attention to the role of humans in overall plant safety. As the regulatory body with primary responsibility for ensuring public health and safety involving nuclear operations, the United States Nuclear Regulatory Commission (NRC) has also become increasingly involved with the ''human'' side of nuclear operations. The purpose of this symposium is to describe a major program of research and technical assistance that the Pacific Northwest Laboratory is performing for the NRC that deals with the issues of safety at nuclear power plants (NPPs). This program addresses safety from several different levels of analysis, which are all important within the context of an integrative approach to system safety

  3. Addressing Unison and Uniqueness of Reliability and Safety for Better Integration

    Science.gov (United States)

    Huang, Zhaofeng; Safie, Fayssal

    2015-01-01

    For a long time, both in theory and in practice, safety and reliability have not been clearly differentiated, which leads to confusion, inefficiency, and sometime counter-productive practices in executing each of these two disciplines. It is imperative to address the uniqueness and the unison of these two disciplines to help both disciplines become more effective and to promote a better integration of the two for enhancing safety and reliability in our products as an overall objective. There are two purposes of this paper. First, it will investigate the uniqueness and unison of each discipline and discuss the interrelationship between the two for awareness and clarification. Second, after clearly understanding the unique roles and interrelationship between the two in a product design and development life cycle, we offer suggestions to enhance the disciplines with distinguished and focused roles, to better integrate the two, and to improve unique sets of skills and tools of reliability and safety processes. From the uniqueness aspect, the paper identifies and discusses the respective uniqueness of reliability and safety from their roles, accountability, nature of requirements, technical scopes, detailed technical approaches, and analysis boundaries. It is misleading to equate unreliable to unsafe, since a safety hazard may or may not be related to the component, sub-system, or system functions, which are primarily what reliability addresses. Similarly, failing-to-function may or may not lead to hazard events. Examples will be given in the paper from aerospace, defense, and consumer products to illustrate the uniqueness and differences between reliability and safety. From the unison aspect, the paper discusses what the commonalities between reliability and safety are, and how these two disciplines are linked, integrated, and supplemented with each other to accomplish the customer requirements and product goals. In addition to understanding the uniqueness in

  4. Toward an integrated system concept for monitoring and evaluation of safety culture

    International Nuclear Information System (INIS)

    Makino, Maomi; Sakaue, Takeharu

    2004-01-01

    The concept of ''nuclear safety culture'' has been advocated and has been much discussed internationally by INSAG (The International Nuclear Safety Advisory Group) under IAEA (the International Atomic Energy Agency) and other institutions since Chernobyl accident. On the safety front, Japan had maintained an excellent track record in nuclear power operations throughout the 1990s. However, there have been a series of new type of problems strongly implying degradation of safety culture, e.g., Monju accident, fire and explosion accident at an Asphalt Solidification Process Facility at Tokai, falsification of annealing data at nuclear power plants (NPP), another data falsification for transport cask of spent fuel and JCO criticality accident. Then the TEPCO (Tokyo Electric Power Company) issue was revealed in 2002. Triggered by this issue, the Nuclear and Industrial Safety Agency (NISA) has been implementing a variety of improvements, one of which was the establishment of a study group in 2003, which invited experts from other fields as well as from nuclear-related industries, to study on how to implement safety culture sufficiently and possible recommendations. Subjects such as the followings piled in the study report will indicate leading keys in case it is going to realize such efforts: ''Foundation of safety culture is a quality management'' and ''Realistic and scientific technique is necessary for the evaluation of safety culture''. In order to respond to these requests, JNES have been advancing the development toward an Integrated System Concept for Monitoring and Evaluation of Safety Culture. This paper describes the outline of the study results reported by the study group and then introduces one of subsystems, SCEST, structuring the integrated system concept for Monitoring and Evaluation of Safety Culture. (author)

  5. Integrated aerosol and thermalhydraulics modelling for CANDU safety analysis

    International Nuclear Information System (INIS)

    McDonald, B.H.; Hanna, B.N.

    1990-08-01

    Analysis of postulated accidents in CANDU reactors that could result in severe fuel damage requires the ability to model the formation of aerosols containing fission product materials and the transport of these aerosols from the fuel, through containment, to any leak to the atmosphere. Best-estimate calculations require intimate coupling and simultaneous solution of all the equations describing the entire range of physical and chemical phenomena involved. The prototype CATHENA/PACE-3D has been developed for integrated calculation of thermalhydraulic and aerosol events in a CANDU reactor during postulated accidents. Examples demonstrate the ability of CATHENA/PACE-3D to produce realistic flow and circulation patterns and reasonable accuracy in solution of two simple fluid-flow test cases for which analytical solutions exist

  6. The integrated criticality safety evaluation for the Hanford tank waste treatment and immobilization plant

    International Nuclear Information System (INIS)

    Losey, D. C.; Miles, R. E.; Perks, M. F.

    2009-01-01

    The Criticality Safety Evaluation Report (CSER) for the Hanford Tank Waste Treatment and Immobilization Plant (WTP) has been developed as a single, integrated evaluation with a scope that covers all of the planned WTP operations. This integrated approach is atypical, as the scopes of criticality evaluations are usually more narrowly defined. Several adjustments were made in developing the WTP CSER, but the primary changes were to provide introductory overview for the criticality safety control strategy and to provide in-depth analysis of the underlying physical and chemical mechanisms that contribute to ensuring safety. The integrated approach for the CSER allowed a more consistent evaluation of safety and avoided redundancies that occur when evaluation is distributed over multiple documents. While the approach used with the WTP CSER necessitated more coordination and teamwork, it has yielded a report is that more integrated and concise than is typical. The integrated approach with the CSER produced a simple criticality control scheme that uses relatively few controls. (authors)

  7. Application of the Integrated Safety Assessment methodology to safety margins. Dynamic Event Trees, Damage Domains and Risk Assessment

    International Nuclear Information System (INIS)

    Ibánez, L.; Hortal, J.; Queral, C.; Gómez-Magán, J.; Sánchez-Perea, M.; Fernández, I.; Meléndez, E.; Expósito, A.; Izquierdo, J.M.; Gil, J.; Marrao, H.; Villalba-Jabonero, E.

    2016-01-01

    The Integrated Safety Assessment (ISA) methodology, developed by the Consejo de Seguridad Nuclear, has been applied to an analysis of Zion NPP for sequences with Loss of the Component Cooling Water System (CCWS). The ISA methodology proposal starts from the unfolding of the Dynamic Event Tree (DET). Results from this first step allow assessing the sequence delineation of standard Probabilistic Safety Analysis results. For some sequences of interest of the outlined DET, ISA then identifies the Damage Domain (DD). This is the region of uncertain times and/or parameters where a safety limit is exceeded, which indicates the occurrence of certain damage situation. This paper illustrates application of this concept obtained simulating sequences with MAAP and with TRACE. From information of simulation results of sequence transients belonging to the DD and the time-density probability distributions of the manual actions and of occurrence of stochastic phenomena, ISA integrates the dynamic reliability equations proposed to obtain the sequence contribution to the global Damage Exceedance Frequency (DEF). Reported results show a slight increase in the DEF for sequences investigated following a power uprate from 100% to 110%. This demonstrates the potential use of the method to help in the assessment of design modifications. - Highlights: • This paper illustrates an application of the ISA methodology to safety margins. • Dynamic Event Trees are useful tool for verifying the standard PSA Event Trees. • The ISA methodology takes into account the uncertainties in human action times. • The ISA methodology shows the Damage Exceedance Frequency increase in power uprates.

  8. Does company size matter? Validation of an integrative model of safety behavior across small and large construction companies.

    Science.gov (United States)

    Guo, Brian H W; Yiu, Tak Wing; González, Vicente A

    2018-02-01

    Previous safety climate studies primarily focused on either large construction companies or the construction industry as a whole, while little is known about whether company size has significant effects on workers' understanding of safety climate measures and relationships between safety climate factors and safety behavior. Thus, this study aims to: (a) test the measurement equivalence (ME) of a safety climate measure across workers from small and large companies; (b) investigate if company size alters the causal structure of the integrative model developed by Guo, Yiu, and González (2016). Data were collected from 253 construction workers in New Zealand using a safety climate measure. This study used multi-group confirmatory factor analyses (MCFA) to test the measurement equivalence of the safety climate measure and structure invariance of the integrative model. Results indicate that workers from small and large companies understood the safety climate measure in a similar manner. In addition, it was suggested that company size does not change the causal structure and mediational processes of the integrative model. Both measurement equivalence of the safety climate measure and structural invariance of the integrative model were supported by this study. Practical applications: Findings of this study provided strong support for a meaningful use of the safety climate measure across construction companies in different sizes. Safety behavior promotion strategies designed based on the integrative model may be well suited for both large and small companies. Copyright © 2017 National Safety Council and Elsevier Ltd. All rights reserved.

  9. Integrated Framework for Patient Safety and Energy Efficiency in Healthcare Facilities Retrofit Projects.

    Science.gov (United States)

    Mohammadpour, Atefeh; Anumba, Chimay J; Messner, John I

    2016-07-01

    There is a growing focus on enhancing energy efficiency in healthcare facilities, many of which are decades old. Since replacement of all aging healthcare facilities is not economically feasible, the retrofitting of these facilities is an appropriate path, which also provides an opportunity to incorporate energy efficiency measures. In undertaking energy efficiency retrofits, it is vital that the safety of the patients in these facilities is maintained or enhanced. However, the interactions between patient safety and energy efficiency have not been adequately addressed to realize the full benefits of retrofitting healthcare facilities. To address this, an innovative integrated framework, the Patient Safety and Energy Efficiency (PATSiE) framework, was developed to simultaneously enhance patient safety and energy efficiency. The framework includes a step -: by -: step procedure for enhancing both patient safety and energy efficiency. It provides a structured overview of the different stages involved in retrofitting healthcare facilities and improves understanding of the intricacies associated with integrating patient safety improvements with energy efficiency enhancements. Evaluation of the PATSiE framework was conducted through focus groups with the key stakeholders in two case study healthcare facilities. The feedback from these stakeholders was generally positive, as they considered the framework useful and applicable to retrofit projects in the healthcare industry. © The Author(s) 2016.

  10. 76 FR 22944 - Pipeline Safety: Notice of Public Webinars on Implementation of Distribution Integrity Management...

    Science.gov (United States)

    2011-04-25

    ... oversight program and operating conditions as well as the evolutionary process that distribution system... 20590. Hand Delivery: Docket Management System, Room W12-140, on the ground floor of the West Building... PHMSA-2011-0084] Pipeline Safety: Notice of Public Webinars on Implementation of Distribution Integrity...

  11. The integral fast reactor (IFR) concept: Physics of operation and safety

    International Nuclear Information System (INIS)

    Wade, D.C.; Chang, Y.I.

    1987-01-01

    The IFR concept employs a pool layout, a U/Pu/Zr metal alloy fuel and a closed fuel cycle based on pyrometallurgical reprocessing and injection casting refabrication. The reactor physics issues of designing for inherent safety and for a closed fissile self-sufficient integral fuel cycle with uranium startup and potential actinide transmutation are discussed

  12. The integral fast reactor (IFR) concept: physics of operation and safety

    International Nuclear Information System (INIS)

    Wade, D.C.; Chang, Y.I.

    1987-01-01

    The IFR concept employs a pool layout, a U/Pu/Zr metal alloy fuel and a closed fuel cycle based on pyrometallurgical reprocessing and injection casting refabrication. The reactor physics issues of designing for inherent safety and for a closed fissile self-sufficient integral fuel cycle with uranium startup and potential actinide transmutation are discussed

  13. Robustness of Supercavitating Vehicles Based on Multistability Analysis

    Directory of Open Access Journals (Sweden)

    Yipin Lv

    2017-01-01

    Full Text Available Supercavity can increase speed of underwater vehicles greatly. However, external interferences always lead to instability of vehicles. This paper focuses on robustness of supercavitating vehicles. Based on a 4-dimensional dynamic model, the existence of multistability is verified in supercavitating system through simulation, and the robustness of vehicles varying with parameters is analyzed by basins of attraction. Results of the research disclose that the supercavitating system has three stable states in some regions of parameters space, namely, stable, periodic, and chaotic states, while in other regions it has various multistability, such as coexistence of two types of stable equilibrium points, coexistence of a limit cycle with a chaotic attractor, and coexistence of 1-periodic cycle with 2-periodic cycle. Provided that cavitation number varies within a small range, with increase of the feedback control gain of fin deflection angle, size of basin of attraction becomes smaller and robustness of the system becomes weaker. In practical application, robustness of supercavitating vehicles can be improved by setting parameters of system or adjusting initial launching conditions.

  14. An Integrated Development Tool for a safety application using FBD language

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Young Jun; Lee, Jang Soo; Lee, Dong Young [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-05-15

    Regarding digitalizing the Nuclear Instrumentation and Control Systems, the application program responsible for the safety functions of Nuclear I and C Systems shall ensure the robustness of the safety function through development, testing, and validation roles for a life cycle process during software development. The importance of software in nuclear systems increases continuously. The integrated engineering tools to develop, test, and validate safety application programs require increasingly more complex parts among a number of components within nuclear digital I and C systems. This paper introduces the integrated engineering tool (SafeCASE-PLC) developed by our project. The SafeCASE-PLC is a kind of software engineering tool to develop, test, and validate the nuclear application program performed in an automatic controller

  15. Integrating animal health and food safety surveillance data from slaughterhouse control.

    Science.gov (United States)

    Lynch, J A; Silva, P

    2013-08-01

    Surveillance at the slaughterhouse level for animal health and food safety purposes encompasses examination for the presence of pathology, pathogens, drug residues, chemical contaminants and antimicrobial resistance. Government, industry and academia are the primary proponents of such surveillance. A variety of policies and policy instruments from voluntary to legislative may be applied to promote or obligate participation. Efforts to integrate data across such diverse organisations encounter significant legal, logistical and financial challenges. Enhancement of policies to encourage effective integration of animal health and food safety surveillance data from slaughterhouse control should promote: a long-term approach; collaboration among government, industry and academia; application of a risk-based scheme; and transparent public access to data, with generation of consumer-oriented communications derived from the data. A strong case can be made that the complementary pursuit of both sustainable animal health and food safety can continue to be aided by surveillance at the slaughterhouse level.

  16. Novel vehicle based on cubosomes for ophthalmic delivery of flurbiprofen with low irritancy and high bioavailability

    Science.gov (United States)

    Han, Shun; Shen, Jin-qiu; Gan, Yong; Geng, Hai-ming; Zhang, Xin-xin; Zhu, Chun-liu; Gan, Li

    2010-01-01

    Aim: To develop a novel vehicle based on cubosomes as an ophthalmic drug delivery system for flurbiprofen (FB) to reduce ocular irritancy and improve bioavailability. Methods: FB-loaded cubosomes were prepared using hot and high-pressure homogenization. Cubosomes were then characterized by particle size, zeta potential, encapsulation efficiency, particle morphology, inner cubic structure and in vitro release. Corneal permeation was evaluated using modified Franz-type cells. Ocular irritation was then evaluated using both the Draize method and histological examination. The ocular pharmacokinetics of FB was determined using microdialysis. Results: The particle size of each cubosome formulation was about 150 nm. A bicontinuous cubic phase of cubic P-type was determined using cryo-transmission electron microscopy (cryo-TEM) observation and small angle X-ray scattering (SAXS) analysis. In vitro corneal permeation study revealed that FB formulated in cubosomes exhibited 2.5-fold (F1) and 2.0-fold (F2) increase in Papp compared with FB PBS. In the ocular irritation test, irritation scores for each group were less than 2, indicating that all formulations exhibited excellent ocular tolerance. Histological examination revealed that neither the structure nor the integrity of the cornea was visibly affected after incubation with FB cubosomes. The AUC of FB administered as FB cubosome F2 was 486.36±38.93 ng·mL−1·min·μg−1, which was significantly higher than that of FB Na eye drops (P<0.01). Compared with FB Na eye drops, the Tmax of FB cubosome F2 was about 1.6-fold higher and the MRT was also significantly longer (P<0.001). Conclusion: This novel low-irritant vehicle based on cubosomes might be a promising system for effective ocular drug delivery. PMID:20686524

  17. Nuclear safety and security culture - an integrated approach to regulatory oversight

    International Nuclear Information System (INIS)

    Tronea, M.; Ciurea Ercau, C.

    2013-01-01

    The paper presents the development and implementation of regulatory guidelines for the oversight of safety and security culture within licensees organizations. CNCAN (the National Commission for Nuclear Activities of Romania) has used the International Atomic Energy Agency (IAEA) attributes for a strong safety culture as the basis for its regulatory guidelines providing support to the reviewers and inspectors for recognizing and gathering information relevant to safety culture. These guidelines are in process of being extended to address also security culture, based on the IAEA Nuclear Security Series No. 7 document Nuclear Security Culture: Implementing Guide. Recognizing that safety and security cultures coexist and need to reinforce each other because they share the common objective of limiting risk and that similar regulatory review and inspection processes are in place for nuclear security oversight, an integrated approach is considered justified, moreover since the common elements of these cultures outweigh the differences. (authors)

  18. Timing of Formal Phase Safety Reviews for Large-Scale Integrated Hazard Analysis

    Science.gov (United States)

    Massie, Michael J.; Morris, A. Terry

    2010-01-01

    Integrated hazard analysis (IHA) is a process used to identify and control unacceptable risk. As such, it does not occur in a vacuum. IHA approaches must be tailored to fit the system being analyzed. Physical, resource, organizational and temporal constraints on large-scale integrated systems impose additional direct or derived requirements on the IHA. The timing and interaction between engineering and safety organizations can provide either benefits or hindrances to the overall end product. The traditional approach for formal phase safety review timing and content, which generally works well for small- to moderate-scale systems, does not work well for very large-scale integrated systems. This paper proposes a modified approach to timing and content of formal phase safety reviews for IHA. Details of the tailoring process for IHA will describe how to avoid temporary disconnects in major milestone reviews and how to maintain a cohesive end-to-end integration story particularly for systems where the integrator inherently has little to no insight into lower level systems. The proposal has the advantage of allowing the hazard analysis development process to occur as technical data normally matures.

  19. THE PLACE OF OCCUPATIONAL HEALTH AND SAFETY MANAGEMENT SYSTEM IN THE INTEGRATED MANAGEMENT SYSTEM

    Directory of Open Access Journals (Sweden)

    Piotr Kafel

    2016-06-01

    Full Text Available The purpose of this paper is to analyze the place of occupational health and safety management system (OHSMS within the integrated management system. Implementation aspects of management systems are discussed, namely the different management system standards used for registration, for example ISO 14001, ISO 9001, OHSAS 18001, ISO 27001, the order in which they were implemented, the time required for each implementation, as well as the scope of integration of these management system standards into a single Integrated Management System and the level of integration. In order to do so, some of the results of a survey carried out in 81 organizations registered to at least two management systems selected from popular international standards, e.g.: ISO 9001, ISO 14001, OHSAS 18001, ISO/IEC 27001, ISO 22000 were used. OHSMS is not the system that is implemented as a first one. Usually it is implemented after or simultaneously with ISO 9001 and ISO 14001 standards. Time of implementation of MSSs in second and further round of implementation is shorter than during the implementation of first standards. There is a higher level of integration of implemented management standards in organizations where one of the standards in OHSMS, than in a companies without OHSMS. The paper analyses those sequences of management systems implementation of safety management systems with other system, that allow organizations to achieve higher levels of integration and presents a possible pattern for the companies initiating the integration process.

  20. A hybrid simulation approach for integrating safety behavior into construction planning: An earthmoving case study.

    Science.gov (United States)

    Goh, Yang Miang; Askar Ali, Mohamed Jawad

    2016-08-01

    One of the key challenges in improving construction safety and health is the management of safety behavior. From a system point of view, workers work unsafely due to system level issues such as poor safety culture, excessive production pressure, inadequate allocation of resources and time and lack of training. These systemic issues should be eradicated or minimized during planning. However, there is a lack of detailed planning tools to help managers assess the impact of their upstream decisions on worker safety behavior. Even though simulation had been used in construction planning, the review conducted in this study showed that construction safety management research had not been exploiting the potential of simulation techniques. Thus, a hybrid simulation framework is proposed to facilitate integration of safety management considerations into construction activity simulation. The hybrid framework consists of discrete event simulation (DES) as the core, but heterogeneous, interactive and intelligent (able to make decisions) agents replace traditional entities and resources. In addition, some of the cognitive processes and physiological aspects of agents are captured using system dynamics (SD) approach. The combination of DES, agent-based simulation (ABS) and SD allows a more "natural" representation of the complex dynamics in construction activities. The proposed hybrid framework was demonstrated using a hypothetical case study. In addition, due to the lack of application of factorial experiment approach in safety management simulation, the case study demonstrated sensitivity analysis and factorial experiment to guide future research. Copyright © 2015 Elsevier Ltd. All rights reserved.

  1. A Study on the Comprehensive and Integrated Workplace Safety and Health Services in Singapore.

    Science.gov (United States)

    Chia, Sin Eng; Wah, Lim John; Khim, Judy Sng Gek; Yoong, Joanne; Lim, Raymond Boon Tar; Seng, Chia Kee

    2015-09-01

    The aim of this study was to evaluate the level of comprehensiveness and integration of workplace safety and health (WSH) services (safety, occupational health, and well-being) in Singapore. Thirty workplaces from five different sectors comprising more than 28,000 workers were assessed using three custom-developed tools. One quarter of the workplaces have applied the principles of comprehensive and integrated WSH. Among those that managed WSH comprehensively, workers were 4.4 times (95% confidence interval [CI], 2.33 to 8.25) more likely to be proud to work for their company, 7.4 times (95% CI, 3.96 to 13.90) more likely to be satisfied with their current job, and 1.7 times (95% CI, 1.21 to 2.32) more likely to balance the demands of work and home. There is a need to enhance awareness and education on comprehensive and integrated WSH in Singapore companies.

  2. Integration profile and safety of an adenovirus hybrid-vector utilizing hyperactive sleeping beauty transposase for somatic integration.

    Directory of Open Access Journals (Sweden)

    Wenli Zhang

    Full Text Available We recently developed adenovirus/transposase hybrid-vectors utilizing the previously described hyperactive Sleeping Beauty (SB transposase HSB5 for somatic integration and we could show stabilized transgene expression in mice and a canine model for hemophilia B. However, the safety profile of these hybrid-vectors with respect to vector dose and genotoxicity remains to be investigated. Herein, we evaluated this hybrid-vector system in C57Bl/6 mice with escalating vector dose settings. We found that in all mice which received the hyperactive SB transposase, transgene expression levels were stabilized in a dose-dependent manner and that the highest vector dose was accompanied by fatalities in mice. To analyze potential genotoxic side-effects due to somatic integration into host chromosomes, we performed a genome-wide integration site analysis using linker-mediated PCR (LM-PCR and linear amplification-mediated PCR (LAM-PCR. Analysis of genomic DNA samples obtained from HSB5 treated female and male mice revealed a total of 1327 unique transposition events. Overall the chromosomal distribution pattern was close-to-random and we observed a random integration profile with respect to integration into gene and non-gene areas. Notably, when using the LM-PCR protocol, 27 extra-chromosomal integration events were identified, most likely caused by transposon excision and subsequent transposition into the delivered adenoviral vector genome. In total, this study provides a careful evaluation of the safety profile of adenovirus/Sleeping Beauty transposase hybrid-vectors. The obtained information will be useful when designing future preclinical studies utilizing hybrid-vectors in small and large animal models.

  3. Nuclear Energy Advanced Modeling and Simulation (NEAMS) Waste Integrated Performance and Safety Codes (IPSC) : FY10 development and integration.

    Energy Technology Data Exchange (ETDEWEB)

    Criscenti, Louise Jacqueline; Sassani, David Carl; Arguello, Jose Guadalupe, Jr.; Dewers, Thomas A.; Bouchard, Julie F.; Edwards, Harold Carter; Freeze, Geoffrey A.; Wang, Yifeng; Schultz, Peter Andrew

    2011-02-01

    This report describes the progress in fiscal year 2010 in developing the Waste Integrated Performance and Safety Codes (IPSC) in support of the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign. The goal of the Waste IPSC is to develop an integrated suite of computational modeling and simulation capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive waste storage or disposal system. The Waste IPSC will provide this simulation capability (1) for a range of disposal concepts, waste form types, engineered repository designs, and geologic settings, (2) for a range of time scales and distances, (3) with appropriate consideration of the inherent uncertainties, and (4) in accordance with robust verification, validation, and software quality requirements. Waste IPSC activities in fiscal year 2010 focused on specifying a challenge problem to demonstrate proof of concept, developing a verification and validation plan, and performing an initial gap analyses to identify candidate codes and tools to support the development and integration of the Waste IPSC. The current Waste IPSC strategy is to acquire and integrate the necessary Waste IPSC capabilities wherever feasible, and develop only those capabilities that cannot be acquired or suitably integrated, verified, or validated. This year-end progress report documents the FY10 status of acquisition, development, and integration of thermal-hydrologic-chemical-mechanical (THCM) code capabilities, frameworks, and enabling tools and infrastructure.

  4. Improving nuclear safety at international research reactors: The Integrated Research Reactor Safety Enhancement Program (IRRSEP)

    International Nuclear Information System (INIS)

    Huizenga, David; Newton, Douglas; Connery, Joyce

    2002-01-01

    Nuclear energy continues to play a major role in the world's energy economy. Research and test reactors are an important component of a nation's nuclear power infrastructure as they provide training, experiments and operating experience vital to developing and sustaining the industry. Indeed, nations with aspirations for nuclear power development usually begin their programs with a research reactor program. Research reactors also are vital to international science and technology development. It is important to keep them safe from both accident and sabotage, not only because of our obligation to prevent human and environmental consequence but also to prevent corresponding damage to science and industry. For example, an incident at a research reactor could cause a political and public backlash that would do irreparable harm to national nuclear programs. Following the accidents at Three Mile Island and Chernobyl, considerable efforts and resources were committed to improving the safety posture of the world's nuclear power plants. Unsafe operation of research reactors will have an amplifying effect throughout a country or region's entire nuclear programs due to political, economic and nuclear infrastructure consequences. (author)

  5. Living up to safety values in health care : The effect of leader behavioral integrity on occupational safety

    NARCIS (Netherlands)

    Halbesleben, J.R.; Leroy, H.; Dierynck, B.; Simons, T.; Savage, G.T.; McCaughey, D.; Leon, M.R.

    2013-01-01

    While previous research has identified that leaders’ safety expectations and safety actions are important in fostering occupational safety, research has yet to demonstrate the importance of leader alignment between safety expectations and actions for improving occupational safety. We build on safety

  6. 48 CFR 952.223-71 - Integration of environment, safety, and health into work planning and execution.

    Science.gov (United States)

    2010-10-01

    ..., safety, and health into work planning and execution. 952.223-71 Section 952.223-71 Federal Acquisition... Provisions and Clauses 952.223-71 Integration of environment, safety, and health into work planning and... safety and health standards applicable to the work conditions of contractor and subcontractor employees...

  7. Integrated Safety Management System Phase I Verification for the Plutonium Finishing Plant (PFP) [VOL 1 and 2

    International Nuclear Information System (INIS)

    SETH, S.S.

    2000-01-01

    U.S. Department of Energy (DOE) Policy 450.4, Safety Management System Policy commits to institutionalizing an Integrated Safety Management System (ISMS) throughout the DOE complex as a means of accomplishing its missions safely. DOE Acquisition Regulation 970.5204-2 requires that contractors manage and perform work in accordance with a documented safety management system

  8. 49 CFR 244.15 - Subjects to be addressed in a Safety Integration Plan not involving an amalgamation of operations.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 4 2010-10-01 2010-10-01 false Subjects to be addressed in a Safety Integration... Regulations Relating to Transportation (Continued) FEDERAL RAILROAD ADMINISTRATION, DEPARTMENT OF TRANSPORTATION REGULATIONS ON SAFETY INTEGRATION PLANS GOVERNING RAILROAD CONSOLIDATIONS, MERGERS, AND...

  9. Risk and Work Configuration Management as a Function of Integrated Safety Management

    International Nuclear Information System (INIS)

    Lana Buehrer; Michele Kelly; Fran Lemieux; Fred Williams

    2007-01-01

    National Security Technologies, LLC (NSTec), has established a work management program and corresponding electronic Facilities and Operations Management Information System (e-FOM) to implement Integrated Safety Management (ISM). The management of work scopes, the identification of hazards, and the establishment of implementing controls are reviewed and approved through electronic signatures. Through the execution of the program and the implementation of the electronic system, NSTec staff work within controls and utilize feedback and improvement process. The Integrated Work Control Manual further implements the five functions of ISM at the Activity level. By adding the Risk and Work Configuration Management program, NSTec establishes risk acceptance (business and physical) for liabilities within the performance direction and work management processes. Requirements, roles, and responsibilities are specifically identified in the program while e-FOM provides the interface and establishes the flowdown from the Safety Chain to work and facilities management processes to company work-related directives, and finally to Subject Matter Expert concurrence. The Program establishes, within the defined management structure, management levels for risk identification, risk mitigation (controls), and risk acceptance (business and physical) within the Safety Chain of Responsibility. The Program also implements Integrated Safeguards and Security Management within the NSTec Safety Chain of Responsibility. Once all information has been entered into e-FOM, approved, and captured as data, the information becomes searchable and sortable by hazard, location, organization, mitigating controls, etc

  10. Extrinsic Calibration for Vehicle-based Mobile Mapping System

    Directory of Open Access Journals (Sweden)

    SHI Limei

    2015-01-01

    Full Text Available Having the advantage of 360° imaging and rotation invariance, panoramic camera has gradually been used in mobile mapping systems(MMS. Calibration is an essential requirement to make sure that MMS can get high quality geo-information. This paper presents a way to address the extrinsic calibration for vehicle-based MMS composed of panoramic camera and Position and Orientation System (POS. Firstly, control points in the natural scene are set up, whose spatial coordinates are measured with high precision. Secondly, a panoramic spherical model is constructed and panoramic image can be projected to this model by means of spherical reverse transformation projection. Then, localize and select the control points in 3D spherical panoramic view but not in panoramic distorted image directly, the spherical coordinates of control points in panoramic image are gotten. After points correspondence is established, make use of direct geo-reference positioning equation and coordinate transformation, the translation and rotation parameters of panoramic camera relative to POS are computed. Experiments are conducted separately in space city calibration site located in Beijing and the Binhai New Area in Tianjin using our approach. Test results are listed as follows. When the GPS signal are of good quality, absolute positioning mean square error of a point is 10.3 cm in two-dimension plane and 16.5 cm in height direction; Otherwise, it is 35.4 cm in two-dimension plane and 54.8 cm in height direction. The max relative error of distance measurement is about 5 cm over a short distance (distance<3 km, which is not obviously affected by the GPS signal quality.

  11. An Integrated Approach of Model checking and Temporal Fault Tree for System Safety Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Koh, Kwang Yong; Seong, Poong Hyun [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

    2009-10-15

    Digitalization of instruments and control systems in nuclear power plants offers the potential to improve plant safety and reliability through features such as increased hardware reliability and stability, and improved failure detection capability. It however makes the systems and their safety analysis more complex. Originally, safety analysis was applied to hardware system components and formal methods mainly to software. For software-controlled or digitalized systems, it is necessary to integrate both. Fault tree analysis (FTA) which has been one of the most widely used safety analysis technique in nuclear industry suffers from several drawbacks as described in. In this work, to resolve the problems, FTA and model checking are integrated to provide formal, automated and qualitative assistance to informal and/or quantitative safety analysis. Our approach proposes to build a formal model of the system together with fault trees. We introduce several temporal gates based on timed computational tree logic (TCTL) to capture absolute time behaviors of the system and to give concrete semantics to fault tree gates to reduce errors during the analysis, and use model checking technique to automate the reasoning process of FTA.

  12. IMPLEMENTING AN INTEGRATED HEALTH, SAFETY, AND ENVIRONMENTAL MANAGEMENT SYSTEM: THE CASE OF A CONSTRUCTION COMPANY

    Directory of Open Access Journals (Sweden)

    Filippos Tepaskoualos

    2017-12-01

    Full Text Available Over the past two decades, there has been an increasing trend of organizations implementing simultaneously two or more management systems. The structural similarities of these systems - despite the diversity of their fields of application, such as occupational health and safety for OHSAS 18001, and environmental management for ISO 14001 - have enabled many organizations to integrate different systems into a single one, rather than implementing them separately from one another. The purpose of this paper is to examine in depth a case of integration of the ISO 14001 and OHSAS 18001 systems, using a construction company as a research setting, in order to draw conclusions about the level of integration achieved, as well as the benefits, the problems, and the critical success factors of this endeavour. The findings of this study show that both the company's devotion to the fulfillment of the critical success factors and the identical structure of the two systems under consideration have facilitated the successful outcome of integration. However, this does not automatically imply that the company adopted the idea of full integration. Instead, the maximization of integration benefits and the elimination of related problems was achieved through the company's conscious choice to proceed with partial integration, keeping separate manuals, policies, and risk management procedures for each system. This study will be useful in order to understand that partial integration is a perfectly acceptable and realistic solution that, under certain circumstances, may even have a better cost-benefit ratio than full integration.

  13. Integrating risk management and safety culture in a framework for risk informed decision making

    International Nuclear Information System (INIS)

    Nelson, W.R.

    2009-01-01

    Operators and regulators of nuclear power plants agree on the importance of maintaining safety and controlling accident risks. Effective safety and risk management requires treatment of both technical and organizational components. Probabilistic Risk Assessment (PRA) provides tools for technical risk management. However, organizational factors are not treated in PRA, but are addressed using different approaches. To bring both components together, a framework of Risk Informed Decision Making (RIDM) is needed. The objective tree structure of the International Atomic Energy Agency (IAEA) is a promising approach to combine both elements. Effective collaboration involving regulatory and industry groups is needed to accomplish the integration. (author)

  14. Fluor Daniel Hanford Inc. integrated safety management system phase 1 verification final report

    International Nuclear Information System (INIS)

    PARSONS, J.E.

    1999-01-01

    The purpose of this review is to verify the adequacy of documentation as submitted to the Approval Authority by Fluor Daniel Hanford, Inc. (FDH). This review is not only a review of the Integrated Safety Management System (ISMS) System Description documentation, but is also a review of the procedures, policies, and manuals of practice used to implement safety management in an environment of organizational restructuring. The FDH ISMS should support the Hanford Strategic Plan (DOE-RL 1996) to safely clean up and manage the site's legacy waste; deploy science and technology while incorporating the ISMS theme to ''Do work safely''; and protect human health and the environment

  15. Integrating Quality and Safety Competencies to Improve Outcomes: Application in Infusion Therapy Practice.

    Science.gov (United States)

    Sherwood, Gwen; Nickel, Barbara

    Despite intense scrutiny and process improvement initiatives, patient harm continues to occur in health care with alarming frequency. The Quality and Safety Education for Nursing (QSEN) project provides a roadmap to transform nursing by integrating 6 competencies: patient-centered care, teamwork and collaboration, evidence-based practice, quality improvement, safety, and informatics. As front-line caregivers, nurses encounter inherent risks in their daily work. Infusion therapy is high risk with multiple potential risks for patient harm. This study examines individual and system application of the QSEN competencies and the Infusion Nurses Society's 2016 Infusion Therapy Standards of Practice in the improvement of patient outcomes.

  16. Idaho National Laboratory Integrated Safety Management System FY 2013 Effectiveness Review and Declaration Report

    Energy Technology Data Exchange (ETDEWEB)

    Hunt, Farren [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2013-12-01

    Idaho National Laboratory (INL) performed an Annual Effectiveness Review of the Integrated Safety Management System (ISMS), per 48 Code of Federal Regulations (CFR) 970.5223 1, “Integration of Environment, Safety and Health into Work Planning and Execution.” The annual review assessed Integrated Safety Management (ISM) effectiveness, provided feedback to maintain system integrity, and identified target areas for focused improvements and assessments for Fiscal Year (FY) 2014. Results of the FY 2013 annual effectiveness review demonstrate that the INL’s ISMS program is “Effective” and continually improving and shows signs of being significantly strengthened. Although there have been unacceptable serious events in the past, there has also been significant attention, dedication, and resources focused on improvement, lessons learned and future prevention. BEA’s strategy of focusing on these improvements includes extensive action and improvement plans that include PLN 4030, “INL Sustained Operational Improvement Plan, PLN 4058, “MFC Strategic Excellence Plan,” PLN 4141, “ATR Sustained Excellence Plan,” and PLN 4145, “Radiological Control Road to Excellence,” and the development of LWP 20000, “Conduct of Research.” As a result of these action plans, coupled with other assurance activities and metrics, significant improvement in operational performance, organizational competence, management oversight and a reduction in the number of operational events is being realized. In short, the realization of the fifth core function of ISMS (feedback and continuous improvement) and the associated benefits are apparent.

  17. Study concerning the power plant control and safety equipment by integrated distributed systems

    International Nuclear Information System (INIS)

    Optea, I.; Oprea, M.; Stanescu, P.

    1995-01-01

    The paper deals with the trends existing in the field of nuclear control and safety equipment and systems, proposing a high-efficiency integrated system. In order to enhance the safety of the plant and reliability of the structure system and components, we present a concept based on the latest computer technology with an open, distributed system, connected by a local area network with high redundancy. A modern conception for the control and safety system is to integrate all the information related to the reactor protection, active engineered safeguard and auxiliary systems parameters, offering a fast flow of information between all the agencies concerned so that situations can be quickly assessed. The integrated distributed control is based on a high performance operating system for realtime applications, flexible enough for transparent networking and modular for demanding configurations. The general design considerations for nuclear reactors instrumentation reliability and testing methods for real-time functions under dynamic regime are presented. Taking into account the fast progress in information technology, we consider the replacement of the old instrumentation of Cernavoda-1 NPP by a modern integrated system as an economical and efficient solution for the next units. (Author) 20 Refs

  18. Fusion integral experiments and analysis and the determination of design safety factors - I: Methodology

    International Nuclear Information System (INIS)

    Youssef, M.Z.; Kumar, A.; Abdou, M.A.; Oyama, Y.; Maekawa, H.

    1995-01-01

    The role of the neutronics experimentation and analysis in fusion neutronics research and development programs is discussed. A new methodology was developed to arrive at estimates to design safety factors based on the experimental and analytical results from design-oriented integral experiments. In this methodology, and for a particular nuclear response, R, a normalized density function (NDF) is constructed from the prediction uncertainties, and their associated standard deviations, as found in the various integral experiments where that response, R, is measured. Important statistical parameters are derived from the NDF, such as the global mean prediction uncertainty, and the possible spread around it. The method of deriving safety factors from many possible NDFs based on various calculational and measuring methods (among other variants) is also described. Associated with each safety factor is a confidence level, designers may choose to have, that the calculated response, R, will not exceed (or will not fall below) the actual measured value. An illustrative example is given on how to construct the NDFs. The methodology is applied in two areas, namely the line-integrated tritium production rate and bulk shielding integral experiments. Conditions under which these factors could be derived and the validity of the method are discussed. 72 refs., 17 figs., 4 tabs

  19. Safety, reliability, risk management and human factors: an integrated engineering approach applied to nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Vasconcelos, Vanderley de; Silva, Eliane Magalhaes Pereira da; Costa, Antonio Carlos Lopes da; Reis, Sergio Carneiro dos [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)], e-mail: vasconv@cdtn.br, e-mail: silvaem@cdtn.br, e-mail: aclc@cdtn.br, e-mail: reissc@cdtn.br

    2009-07-01

    Nuclear energy has an important engineering legacy to share with the conventional industry. Much of the development of the tools related to safety, reliability, risk management, and human factors are associated with nuclear plant processes, mainly because the public concern about nuclear power generation. Despite the close association between these subjects, there are some important different approaches. The reliability engineering approach uses several techniques to minimize the component failures that cause the failure of the complex systems. These techniques include, for instance, redundancy, diversity, standby sparing, safety factors, and reliability centered maintenance. On the other hand system safety is primarily concerned with hazard management, that is, the identification, evaluation and control of hazards. Rather than just look at failure rates or engineering strengths, system safety would examine the interactions among system components. The events that cause accidents may be complex combinations of component failures, faulty maintenance, design errors, human actions, or actuation of instrumentation and control. Then, system safety deals with a broader spectrum of risk management, including: ergonomics, legal requirements, quality control, public acceptance, political considerations, and many other non-technical influences. Taking care of these subjects individually can compromise the completeness of the analysis and the measures associated with both risk reduction, and safety and reliability increasing. Analyzing together the engineering systems and controls of a nuclear facility, their management systems and operational procedures, and the human factors engineering, many benefits can be realized. This paper proposes an integration of these issues based on the application of systems theory. (author)

  20. Safety, reliability, risk management and human factors: an integrated engineering approach applied to nuclear facilities

    International Nuclear Information System (INIS)

    Vasconcelos, Vanderley de; Silva, Eliane Magalhaes Pereira da; Costa, Antonio Carlos Lopes da; Reis, Sergio Carneiro dos

    2009-01-01

    Nuclear energy has an important engineering legacy to share with the conventional industry. Much of the development of the tools related to safety, reliability, risk management, and human factors are associated with nuclear plant processes, mainly because the public concern about nuclear power generation. Despite the close association between these subjects, there are some important different approaches. The reliability engineering approach uses several techniques to minimize the component failures that cause the failure of the complex systems. These techniques include, for instance, redundancy, diversity, standby sparing, safety factors, and reliability centered maintenance. On the other hand system safety is primarily concerned with hazard management, that is, the identification, evaluation and control of hazards. Rather than just look at failure rates or engineering strengths, system safety would examine the interactions among system components. The events that cause accidents may be complex combinations of component failures, faulty maintenance, design errors, human actions, or actuation of instrumentation and control. Then, system safety deals with a broader spectrum of risk management, including: ergonomics, legal requirements, quality control, public acceptance, political considerations, and many other non-technical influences. Taking care of these subjects individually can compromise the completeness of the analysis and the measures associated with both risk reduction, and safety and reliability increasing. Analyzing together the engineering systems and controls of a nuclear facility, their management systems and operational procedures, and the human factors engineering, many benefits can be realized. This paper proposes an integration of these issues based on the application of systems theory. (author)

  1. Safety

    International Nuclear Information System (INIS)

    1998-01-01

    A brief account of activities carried out by the Nuclear power plants Jaslovske Bohunice in 1997 is presented. These activities are reported under the headings: (1) Nuclear safety; (2) Industrial and health safety; (3) Radiation safety; and Fire protection

  2. Passive Decay Heat Removal Strategy of Integrated Passive Safety System (IPSS) for SBO-combined Accidents

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sang Ho; Chang, Soon Heung; Jeong, Yong Hoon [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

    2014-10-15

    The weak points of nuclear safety would be in outmoded nuclear power plants like the Fukushima reactors. One of the systems for the safety enhancement is integrated passive safety system (IPSS) proposed after the Fukushima accidents. It has the five functions for the prevention and mitigation of a severe accident. Passive decay heat removal (PDHR) strategy using IPSS is proposed for coping with SBO-combined accidents in this paper. The two systems for removing decay heat before core-melt were applied in the strategy. The accidents were simulated by MARS code. The reference reactor was OPR1000, specifically Ulchin-3 and 4. The accidents included loss-of-coolant accidents (LOCA) because the coolant losses could be occurred in the SBO condition. The examples were the stuck open of PSV, the abnormal open of SDV and the leakage of RCP seal water. Also, as LOCAs with the failure of active safety injection systems were considered, various LOCAs were simulated in SBO. Based on the thermal hydraulic analysis, the probabilistic safety analysis was carried out for the PDHR strategy to estimate the safety enhancement in terms of the variation of core damage frequency. AIMS-PSA developed by KAERI was used for calculating CDF of the plant. The IPSS was applied in the PDHR strategy which was developed in order to cope with the SBO-combined accidents. The estimation for initiating SGGI or PSIS was based on the pressure in RCS. The simulations for accidents showed that the decay heat could be removed for the safety duration time in SBO. The increase of safety duration time from the strategy provides the increase of time for the restoration of AC power.

  3. Idaho National Laboratory Integrated Safety Management System FY 2016 Effectiveness Review and Declaration Report

    Energy Technology Data Exchange (ETDEWEB)

    Hunt, Farren J. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-12-01

    Idaho National Laboratory’s (INL’s) Integrated Safety Management System (ISMS) effectiveness review of fiscal year (FY) 2016 shows that INL has integrated management programs and safety elements throughout the oversight and operational activities performed at INL. The significant maturity of Contractor Assurance System (CAS) processes, as demonstrated across INL’s management systems and periodic reporting through the Management Review Meeting process, over the past two years has provided INL with current real-time understanding and knowledge pertaining to the health of the institution. INL’s sustained excellence of the Integrated Safety and effective implementation of the Worker Safety and Health Program is also evidenced by other external validations and key indicators. In particular, external validations include VPP, ISO 14001, DOELAP accreditation, and key Laboratory level indicators such as ORPS (number, event frequency and severity); injury/illness indicators such as Days Away, Restricted and Transfer (DART) case rate, back & shoulder metric and open reporting indicators, demonstrate a continuous positive trend and therefore improved operational performance over the last few years. These indicators are also reflective of the Laboratory’s overall organizational and safety culture improvement. Notably, there has also been a step change in ESH&Q Leadership actions that have been recognized both locally and complex-wide. Notwithstanding, Laboratory management continues to monitor and take action on lower level negative trends in numerous areas including: Conduct of Operations, Work Control, Work Site Analysis, Risk Assessment, LO/TO, Fire Protection, and Life Safety Systems, to mention a few. While the number of severe injury cases has decreased, as evidenced by the reduction in the DART case rate, the two hand injuries and the fire truck/ambulance accident were of particular concern. Aggressive actions continue in order to understand the causes and

  4. Idaho National Laboratory Integrated Safety Management System FY 2016 Effectiveness Review and Declaration Report

    International Nuclear Information System (INIS)

    Hunt, Farren J.

    2016-01-01

    Idaho National Laboratory's (INL's) Integrated Safety Management System (ISMS) effectiveness review of fiscal year (FY) 2016 shows that INL has integrated management programs and safety elements throughout the oversight and operational activities performed at INL. The significant maturity of Contractor Assurance System (CAS) processes, as demonstrated across INL's management systems and periodic reporting through the Management Review Meeting process, over the past two years has provided INL with current real-time understanding and knowledge pertaining to the health of the institution. INL's sustained excellence of the Integrated Safety and effective implementation of the Worker Safety and Health Program is also evidenced by other external validations and key indicators. In particular, external validations include VPP, ISO 14001, DOELAP accreditation, and key Laboratory level indicators such as ORPS (number, event frequency and severity); injury/illness indicators such as Days Away, Restricted and Transfer (DART) case rate, back & shoulder metric and open reporting indicators, demonstrate a continuous positive trend and therefore improved operational performance over the last few years. These indicators are also reflective of the Laboratory's overall organizational and safety culture improvement. Notably, there has also been a step change in ESH&Q Leadership actions that have been recognized both locally and complex-wide. Notwithstanding, Laboratory management continues to monitor and take action on lower level negative trends in numerous areas including: Conduct of Operations, Work Control, Work Site Analysis, Risk Assessment, LO/TO, Fire Protection, and Life Safety Systems, to mention a few. While the number of severe injury cases has decreased, as evidenced by the reduction in the DART case rate, the two hand injuries and the fire truck/ambulance accident were of particular concern. Aggressive actions continue in order to understand the causes and define actions

  5. Lessons in Nuclear Safety, Panel on Integration of People and Programs

    International Nuclear Information System (INIS)

    Pinkston, David

    2015-01-01

    Four slides present a historical perspective on the evolution of nuclear safety, a description of systemic misalignment (available resources do not match expectations, demographic cliff developing, promulgation of increased expectations and new requirements proceeds unabated), and needs facing nuclear safety (financial stability, operational stability, and succession planning). The following conclusions are stated under the heading ''Nuclear Safety - 'The System''': the current universe of requirements is too large for the resource pool available; the current universe of requirements has too many different sources of interpretation; there are so many indicators that it's hard to know what is leading (or important); and the net result can come to defy integrated comprehension at the worker level.

  6. Regulatory Oversight of Radioactive Sources through the Integrated Management of Safety and Security

    International Nuclear Information System (INIS)

    Horvath, K.

    2016-01-01

    The Hungarian Atomic Energy Authority (HAEA) has full regulatory competence; its mission is to oversee the safety and security of all the peaceful applications of atomic energy. All the radioactive sources having activity above the exemption level is registered and licensed both from safety and security points of view. The Hungarian central register of radioactive sources contains about 7,000 radioactive sources and 450 license holders. In order to use its limited resources the HAEA has decided to introduce an integrated regulatory oversight programme. Accordingly, during the licensing process and inspection activities the HAEA intends to assess both safety and security aspects at the same time. The article describes the Hungarian the various applications of radioactive materials, and summarizes the preparation activities of the HAEA. (author)

  7. Knowledge, attitudes and practices of food handlers in food safety: An integrative review.

    Science.gov (United States)

    Zanin, Laís Mariano; da Cunha, Diogo Thimoteo; de Rosso, Veridiana Vera; Capriles, Vanessa Dias; Stedefeldt, Elke

    2017-10-01

    This study presents an overview of the relationship between knowledge, attitudes and practices (KAP) of food handlers with training in food safety, in addition to proposing reflections on the training of food handlers, considering its responsibility for food safety and health of consumers. The review was based on the integrative method. The descriptors used were: (food handler), (knowledge, attitudes and practice) and (training). Six databases were searched, 253 articles were consulted and 36 original articles were included. Fifty per cent of the articles pointed that there was no proper translation of knowledge into attitudes/practices or attitudes into practices after training. Knowledge, attitudes and practices of food handlers are important for identifying how efficient training in food safety is allowing prioritize actions in planning training. The evaluation of KAP is the first step to understand the food handler's point of view. After this evaluation other diagnostic strategies become necessary to enhance this understanding. Copyright © 2017. Published by Elsevier Ltd.

  8. Integrated Plant Safety Assessment, Systematic Evaluation Program, Palisades Plant (Docket No. 50-255)

    International Nuclear Information System (INIS)

    1983-11-01

    This report documents the review completed under the SEP for those issues that required refined engineering evaluations or the continuation of ongoing evaluations after the Final IPSAR for the Palisades Plant was issued. The review has provided for (1) an assessment of the significance of differences between current technical positions on selected safety issues and those that existed when the Palisades Plant was licensed, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety when the supplement to the Final IPSAR and the Safety Evaluation Report for converting the license from a provisional to a full-term license have been issued. The Final IPSAR and its supplement will form part of the bases for considering the conversion of the provisional operating license to a full-term operating license

  9. A risk characterization of safety research areas for integral fast reactor program planning

    International Nuclear Information System (INIS)

    Mueller, C.J.; Cahalan, J.E.; Hill, D.J.; Kramer, J.M.; Marchaterre, J.F.; Pedersen, D.R.; Sevy, R.H.; Tibbrook, R.W.; Wei, T.Y.; Wright, A.E.

    1988-01-01

    This paper characterizes the areas of integral fast reactor (IFR) safety research in terms of their importance in addressing the risk of core disruption sequences for innovative designs. Such sequences have traditionally been determined to constitute the primary risk to public health and safety. All core disruption sequences are folded into four fault categories: classic unprotected (unscrammed) events; loss of decay heat; local fault propagation; and failure to critical reactor structures. Event trees are used to describe these sequences and the areas in the IFR safety and related base technology research programs are discussed with respect to their relevance in addressing the key issues in preventing or delimiting core disruptive sequences. Thus a measure of potential for risk reduction is obtained for guidance in establishing research priorities

  10. Integrating Safety in the Aviation System: Interdepartmental Training for Pilots and Maintenance Technicians

    Science.gov (United States)

    Mattson, Marifran; Petrin, Donald A.; Young, John P.

    2001-01-01

    The study of human factors has had a decisive impact on the aviation industry. However, the entire aviation system often is not considered in researching, training, and evaluating human factors issues especially with regard to safety. In both conceptual and practical terms, we argue for the proactive management of human error from both an individual and organizational systems perspective. The results of a multidisciplinary research project incorporating survey data from professional pilots and maintenance technicians and an exploratory study integrating students from relevant disciplines are reported. Survey findings suggest that latent safety errors may occur during the maintenance discrepancy reporting process because pilots and maintenance technicians do not effectively interact with one another. The importance of interdepartmental or cross-disciplinary training for decreasing these errors and increasing safety is discussed as a primary implication.

  11. A risk characterization of safety research areas for Integral Fast Reactor program planning

    International Nuclear Information System (INIS)

    Mueller, C.J.; Cahalan, J.E.; Hill, D.J.

    1988-01-01

    This paper characterizes the areas of Integral Fast Reactor (IFR) safety research in terms of their importance in addressing the risk of core disruption sequences for innovative designs. Such sequences have traditionally been determined to constitute the primary risk to public health and safety. All core disruption sequences are folded into four fault categories: classic unprotected (unscrammed) events; loss of decay heat; local fault propagation; and failure of critical reactor structures. Event trees are used to describe these sequences and the areas in the IFR Safety and related Base Technology research programs are discussed with respect to their relevance in addressing the key issues in preventing or delimiting core disruptive sequences. Thus a measure of potential for risk reduction is obtained for guidance in establishing research priorites

  12. Results from an Integrated Safety Analysis of Urelumab, an Agonist Anti-CD137 Monoclonal Antibody

    DEFF Research Database (Denmark)

    Segal, Neil H; Logan, Theodore F; Hodi, F Stephen

    2017-01-01

    Purpose: Urelumab is an agonist antibody to CD137 with potential application as an immuno-oncology therapeutic. Data were analyzed to assess safety, tolerability, and pharmacodynamic activity of urelumab, including the dose selected for ongoing development in patients with advanced solid tumors...... and lymphoma.Experimental Design: A total of 346 patients with advanced cancers who had progressed after standard treatment received at least one dose of urelumab in one of three dose-escalation, monotherapy studies. Urelumab was administered at doses ranging from 0.1 to 15 mg/kg. Safety analyses included...... the most common treatment-related AEs, and was associated with immunologic and pharmacodynamic activity demonstrated by the induction of IFN-inducible genes and cytokines.Conclusions: Integrated evaluation of urelumab safety data showed significant transaminitis was strongly associated with doses of ≥1 mg...

  13. Integrated, digital experiment transient control and safety protection of an in-pile test

    International Nuclear Information System (INIS)

    Thomas, R.W.; Whitacre, R.F.; Klingler, W.B.

    1982-01-01

    The Sodium Loop Safety Facility experimental program has demonstrated that in-pile loop fuel failure transient tests can be digitally controlled and protected with reliability and precision. This was done in four nuclear experiments conducted in the Engineering Test Reactor operated by EG and G Idaho, Inc., at the Idaho National Engineering Laboratory. Loop sodium flow and reactor power transients can be programmed to sponsor requirements and verified prior to the test. Each controller has redundancy, which reduces the effect of single failures occurring during test transients. Feedback and reject criteria are included in the reactor power control. Timed sequencing integrates the initiation of the controllers, programmed safety set-points, and other experiment actions (e.g., planned scram). Off-line and on-line testing is included. Loss-of-flow, loss-of-piping-integrity, boiling-window, transient-overpower, and local fault tests have been successfully run using this system

  14. SAFETY: an integrated clinical reasoning and reflection framework for undergraduate nursing students.

    Science.gov (United States)

    Hicks Russell, Bedelia; Geist, Melissa J; House Maffett, Jenny

    2013-01-01

    Nurse educators can no longer focus on imparting to students knowledge that is merely factual and content specific. Activities that provide students with opportunities to apply concepts in real-world scenarios can be powerful tools. Nurse educators should take advantage of student-patient interactions to model clinical reasoning and allow students to practice complex decision making throughout the entire curriculum. In response to this change in nursing education, faculty in a pediatric course designed a reflective clinical reasoning activity based on the SAFETY template, which is derived from the National Council of State Boards of Nursing RN practice analysis. Students were able to prioritize key components of nursing care, as well as integrate practice issues such as delegation, Health Insurance Portability and Accountability Act violations, and questioning the accuracy of orders. SAFETY is proposed as a framework for integration of content knowledge, clinical reasoning, and reflection on authentic professional nursing concerns. Copyright 2012, SLACK Incorporated.

  15. Integrated safety analysis of rolapitant with coadministered drugs from phase II/III trials

    DEFF Research Database (Denmark)

    Barbour, S; Smit, T.; Wang, X

    2017-01-01

    adverse events by use versus non-use of drug substrates of CYP2D6 or BCRP. Patients and methods: Patients were randomized to receive either 180 mg oral rolapitant or placebo approximately 1-2 hours before chemotherapy in combination with a 5-hydroxytryptamine type 3 RA and dexamethasone. Data...... cytochrome P450 (CYP) 3A4, but it does inhibit CYP2D6 and breast cancer resistance protein (BCRP). To analyze potential drug-drug interactions between rolapitant and concomitant medications, this integrated safety analysis of four double-blind, randomized phase II or III studies of rolapitant examined...... for treatment-emergent adverse events (TEAEs) and treatment-emergent serious adverse events (TESAEs) during cycle 1 were pooled across the four studies and summarized in the overall population and by concomitant use/non-use of CYP2D6 or BCRP substrate drugs. Results: In the integrated safety population, 828...

  16. Development of national standards related to the integrated safety and security of high-rise buildings

    Science.gov (United States)

    Voskresenskaya, Elena; Vorona-Slivinskaya, Lubov

    2018-03-01

    The article considers the issues of developing national standards for high-rise construction. The system of standards should provide industrial, operational, economic and terrorist safety of high-rise buildings and facilities. Modern standards of high-rise construction should set the rules for designing engineering systems of high-rise buildings, which will ensure the integrated security of buildings, increase their energy efficiency and reduce the consumption of resources in construction and operation.

  17. Development of national standards related to the integrated safety and security of high-rise buildings

    Directory of Open Access Journals (Sweden)

    Voskresenskaya Elena

    2018-01-01

    Full Text Available The article considers the issues of developing national standards for high-rise construction. The system of standards should provide industrial, operational, economic and terrorist safety of high-rise buildings and facilities. Modern standards of high-rise construction should set the rules for designing engineering systems of high-rise buildings, which will ensure the integrated security of buildings, increase their energy efficiency and reduce the consumption of resources in construction and operation.

  18. Radiation safety infrastructure in developing countries: a proactive approach for integrated and continuous improvement

    International Nuclear Information System (INIS)

    Mrabit, Khammar

    2008-01-01

    The International Atomic Energy Agency (the Agency) is authorized, by its statute, to establish or adopt safety standards for the protection of health and minimization of danger to life and property, and to provide for their application to its own operations as well as to operations under its control or supervision. The Agency has been assisting, since the mid 1960 's, its Member States through mainly its Technical Cooperation Programme (TCP) to improve their national radiation safety infrastructures. However up to the early nineties, assistance was specific and mostly ad hoc and did not systematically utilize an integrated and harmonized approach to achieving effective and sustainable national radiation safety infrastructures in Member States. An unprecedented and integrated international cooperative effort was launched by the Agency in 1994 to establish and/or upgrade the national radiation safety infrastructure in more than 90 countries within the framework of its TCP through the so-called Model project on upgrading radiation protection infrastructure. In this project proactive co-operation with Member States was used in striving towards achieving an effective and sustainable radiation safety infrastructure, compatible with the International basic safety standards for protection against ionizing radiation and for the safety of radiation sources (the BSS) and related standards. Extension to include compatibility with the guidance of the Code of Conduct on the Safety and Security of Radioactive Sources occurred towards the end of the Model Project in December 2004, and with the more recent ensuing follow up projects that started in 2005. The Model Project started with 5 countries in 1994 and finished with 91 countries in 2004. Up to the end of 2007 more than one hundred Member States had been participating in follow up projects covering six themes - namely: legislative and regulatory infrastructure; occupational radiation protection; radiation protection in

  19. IRIS guidelines. 2014 ed. Integrated Review of Infrastructure for Safety (IRIS) for self-assessment when establishing the safety infrastructure for a nuclear power programme

    International Nuclear Information System (INIS)

    2014-01-01

    The IAEA safety standards reflect an international consensus on what constitutes a high level of safety for protecting people and the environment, and therefore represent what all Member States should achieve, whilst recognizing the ultimate responsibility of each State to ensure safety when implementing a nuclear power programme. IAEA Safety Standards Series No. SSG-16, entitled Establishing the Safety Infrastructure for a Nuclear Power Programme was published in order to provide recommendations, presented in the form of sequential actions, on meeting safety requirements progressively during the initial three phases of the development of safety, as described in INSAG-22, Nuclear Safety Infrastructure for a National Nuclear Power Programme Supported by the IAEA Fundamental Safety Principles. To that end, the 200 safety related actions, which are proposed by SSG-16, constitute a roadmap to establish a foundation for promoting a high level of safety over the entire lifetime of the nuclear power plant. These actions reflect international consensus on good practice in order to achieve full implementation of IAEA safety standards. The IAEA has developed a methodology and tool, the Integrated Review of Infrastructure for Safety (IRIS), to assist States in undertaking self-assessment with respect to SSG-16 recommendations when establishing the safety infrastructure for a nuclear power programme, and to develop an action plan for improvement. The IRIS methodology and the associated tool are fully compatible with the IAEA safety standards and are also used, when appropriate, in the preparation of review missions, such as the Integrated Regulatory Review Service and advisory missions. The present guidelines describe the IRIS methodology for self-assessment against SSG-16 recommendations. Through IRIS implementation, every organization concerned with nuclear safety may gain proper awareness and engage in a continuous progressive process to develop the effective national

  20. Analysis of cold leg LOCA with failed HPSI by means of integrated safety assessment methodology

    International Nuclear Information System (INIS)

    Gonzalez-Cadelo, J.; Queral, C.; Montero-Mayorga, J.

    2014-01-01

    Highlights: • Results of ISA for considered sequences endorse EOPs guidance in an original way. • ISA allows to obtain accurate available times for accident management actions. • RCP-trip adequacy and available time for beginning depressurization are evaluated. • ISA minimizes the necessity of expert judgment to perform safety assessment. - Abstract: The integrated safety assessment (ISA) methodology, developed by the Spanish Nuclear Safety Council (CSN), has been applied to a thermal–hydraulic analysis of cold leg LOCA sequences with unavailable High Pressure Injection System in a Westinghouse 3-loop PWR. This analysis has been performed with TRACE 5.0 patch 1 code. ISA methodology allows obtaining the Damage Domain (the region of space of parameters where a safety limit is exceeded) as a function of uncertain parameters (break area) and operator actuation times, and provides to the analyst useful information about the impact of these uncertain parameters in safety concerns. In this work two main issues have been analyzed: the effect of reactor coolant pump trip and the available time for beginning of secondary-side depressurization. The main conclusions are that present Emergency Operating Procedures (EOPs) are adequate for managing this kind of sequences and the ISA methodology is able to take into account time delays and parameter uncertainties

  1. Revamping occupational safety and health training: Integrating andragogical principles for the adult learner

    Directory of Open Access Journals (Sweden)

    Alex Albert

    2013-09-01

    Full Text Available Despite attempts to improve safety performance, the construction industry continues to account for a disproportionate rate of injuries. A large proportion of these injuries occur because workers are unable to recognize and respond to hazards in dynamic and unpredictable environments. Unrecognized hazards expose workers to unanticipated risks and can lead to catastrophic accidents. In order to enhance hazard recognition skills, employers often put new and experienced workers through formal hazard recognition training programs. Unfortunately, current training programs primarily rely on instructor-centric pedagogical approaches, which are insensitive to the adult learning process. In order to ensure effective adult learning, training programs must integrate learner-centric andragogical principles to improve engagement and retention in adult trainees. This paper aims to discuss training program elements that can potentially accelerate the adult learning process while improving safety knowledge retention. To this end, the researchers reviewed relevant literature on the cognitive processes of adult learning, essential components of effectual training programs and developed a reliable framework for the training and transfer of safety knowledge. A case example of successfully using the framework is also presented. The results of the study will provide safety trainers and construction professionals with valuable information on developing effective hazard recognition and receptor training programs, with the goal of improving construction safety performance.

  2. The application of integrated safety management principles to the Tritium Extraction Facility project

    International Nuclear Information System (INIS)

    Hickman, M.O.; Viviano, R.R.

    2000-01-01

    The DOE has developed a program that is accomplishing a heightened safety posture across the complex. The Integrated Safety Management (ISM) System (ISMS) program utilizes five core functions and seven guiding principles as the basis for implementation. The core functions define the work scope, analyze the hazards, develop and implement hazard controls, perform the work, and provide feedback for improvement. The guiding principles include line management responsibility, clear roles and responsibilities, competence per responsibilities, identification of safety standards/requirements, tailored hazard control, balanced priorities, and operations authorization. There exists an unspecified eighth principle, that is, worker involvement. A program requiring the direct involvement of the employees who are actually performing the work has been shown to be quite an effective method of communicating safety requirements, controlling work in a safe manner, and reducing safety violations and injuries. The Tritium Extraction Facility (TEF) projects, a component of the DOE's Commercial Light Water Reactor Tritium Production program, has taken the ISM principles and core functions and applied them to the project's design. The task of the design team is to design a facility and systems that will meet the production requirements of the DOE tritium mission as well as a design that minimizes the workers' exposure to adverse safety situations and hazards/hazardous materials. During the development of the preliminary design for the TEF, design teams consisted of not only designers but also personnel who had operational experience in the existing tritium and personnel who had operational experience in the existing tritium and personnel who had specialized experience from across the DOE complex. This design team reviewed multiple documents associated with the TEF operation in order to identify and document the hazards associated with the tritium process. These documents include hazards

  3. NMC and A and nuclear criticality safety systems integration: A prospective way for enhancement of the nuclear industry facilities safety

    International Nuclear Information System (INIS)

    Ryazanov, Boris G.; Sviridov, Victor I.; Frolov, Vladimir V.; Shvedov, Maxim O.; Mclaughlin, Thomas P.; Pruvost, Norman L.

    2003-01-01

    the necessity and usefulness of integrating measures and components of MC and A and nuclear safety systems to meet the goals faced by both systems. (author)

  4. 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

  5. Validation and Verification of Future Integrated Safety-Critical Systems Operating under Off-Nominal Conditions

    Science.gov (United States)

    Belcastro, Christine M.

    2010-01-01

    Loss of control remains one of the largest contributors to aircraft fatal accidents worldwide. Aircraft loss-of-control accidents are highly complex in that they can result from numerous causal and contributing factors acting alone or (more often) in combination. Hence, there is no single intervention strategy to prevent these accidents and reducing them will require a holistic integrated intervention capability. Future onboard integrated system technologies developed for preventing loss of vehicle control accidents must be able to assure safe operation under the associated off-nominal conditions. The transition of these technologies into the commercial fleet will require their extensive validation and verification (V and V) and ultimate certification. The V and V of complex integrated systems poses major nontrivial technical challenges particularly for safety-critical operation under highly off-nominal conditions associated with aircraft loss-of-control events. This paper summarizes the V and V problem and presents a proposed process that could be applied to complex integrated safety-critical systems developed for preventing aircraft loss-of-control accidents. A summary of recent research accomplishments in this effort is also provided.

  6. Integration of Active and Passive Safety Technologies--A Method to Study and Estimate Field Capability.

    Science.gov (United States)

    Hu, Jingwen; Flannagan, Carol A; Bao, Shan; McCoy, Robert W; Siasoco, Kevin M; Barbat, Saeed

    2015-11-01

    The objective of this study is to develop a method that uses a combination of field data analysis, naturalistic driving data analysis, and computational simulations to explore the potential injury reduction capabilities of integrating passive and active safety systems in frontal impact conditions. For the purposes of this study, the active safety system is actually a driver assist (DA) feature that has the potential to reduce delta-V prior to a crash, in frontal or other crash scenarios. A field data analysis was first conducted to estimate the delta-V distribution change based on an assumption of 20% crash avoidance resulting from a pre-crash braking DA feature. Analysis of changes in driver head location during 470 hard braking events in a naturalistic driving study found that drivers' head positions were mostly in the center position before the braking onset, while the percentage of time drivers leaning forward or backward increased significantly after the braking onset. Parametric studies with a total of 4800 MADYMO simulations showed that both delta-V and occupant pre-crash posture had pronounced effects on occupant injury risks and on the optimal restraint designs. By combining the results for the delta-V and head position distribution changes, a weighted average of injury risk reduction of 17% and 48% was predicted by the 50th percentile Anthropomorphic Test Device (ATD) model and human body model, respectively, with the assumption that the restraint system can adapt to the specific delta-V and pre-crash posture. This study demonstrated the potential for further reducing occupant injury risk in frontal crashes by the integration of a passive safety system with a DA feature. Future analyses considering more vehicle models, various crash conditions, and variations of occupant characteristics, such as age, gender, weight, and height, are necessary to further investigate the potential capability of integrating passive and DA or active safety systems.

  7. Intelligent vehicle based traffic monitoring – exploring application in South Africa

    CSIR Research Space (South Africa)

    Labuschagne, FJJ

    2010-08-01

    Full Text Available The paper details the anticipated benefits of an intelligent vehicle based traffic monitoring approach holds. The approach utilises advanced technology with the potential to reduce crashes and includes the monitor of vehicle speeds and flows...

  8. Risk-Informed Safety Margin Characterization (RISMC): Integrated Treatment of Aleatory and Epistemic Uncertainty in Safety Analysis

    International Nuclear Information System (INIS)

    Youngblood, R.W.

    2010-01-01

    The concept of 'margin' has a long history in nuclear licensing and in the codification of good engineering practices. However, some traditional applications of 'margin' have been carried out for surrogate scenarios (such as design basis scenarios), without regard to the actual frequencies of those scenarios, and have been carried out with in a systematically conservative fashion. This means that the effectiveness of the application of the margin concept is determined in part by the original choice of surrogates, and is limited in any case by the degree of conservatism imposed on the evaluation. In the RISMC project, which is part of the Department of Energy's 'Light Water Reactor Sustainability Program' (LWRSP), we are developing a risk-informed characterization of safety margin. Beginning with the traditional discussion of 'margin' in terms of a 'load' (a physical challenge to system or component function) and a 'capacity' (the capability of that system or component to accommodate the challenge), we are developing the capability to characterize probabilistic load and capacity spectra, reflecting both aleatory and epistemic uncertainty in system response. For example, the probabilistic load spectrum will reflect the frequency of challenges of a particular severity. Such a characterization is required if decision-making is to be informed optimally. However, in order to enable the quantification of probabilistic load spectra, existing analysis capability needs to be extended. Accordingly, the INL is working on a next-generation safety analysis capability whose design will allow for much more efficient parameter uncertainty analysis, and will enable a much better integration of reliability-related and phenomenology-related aspects of margin.

  9. Regional Integrated Tenets to Reinforce the Safety and Security of Radioactive Sources (ClearZone)

    International Nuclear Information System (INIS)

    Salzer, P.

    2003-01-01

    The EURATOM Research and Training Programme on Nuclear Energy includes 2 main fields - fusion energy research and management of radioactive waste, radiation protection and other activities of nuclear technology and safety.Seven instruments (mechanisms) for projects management are used - 'Network of Excellence' (NOE); 'Integrated Project' (IP); 'Specific Targeted Research Project' or 'Specific Targeted Training Project' (STREP); 'Co-ordination Action' (CA); Actions to Promote and Develop Human Resources and Mobility Specific Support Actions; Integrated Infrastructure Initiatives. Two consecutive sub-projects are proposed: 'small' - countries of the Visegrad four + Austrian participant -within the 6th FP 'Specific Supported Actions' and 'large' - participation of more countries in the region - more oriented to practical implementation of the 'small' project findings - intention to use the 6th Framework Programme resources to co-financing the implementation activities. The main objectives are: to create effective lines of defense (prevention -detection - categorization - transport - storage) against malicious use of radioactive sources; to achieve and maintain a high level of safety and security of radioactive sources; to arise the radioactive sources management safety and security culture at the Central European region. Consortium of 11 organisations from Czech Republic, Slovak Republic, Austria, Hungary and Poland is established for the Project implementation. The Project task are grouped in the following areas: legislation, infrastructure, practices; metallurgical industry, cross border control; instrumentation and metrology; information system

  10. Framework for Integrating Safety, Operations, Security, and Safeguards in the Design and Operation of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Darby, John L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Horak, Karl Emanuel [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); LaChance, Jeffrey L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Tolk, Keith Michael [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Whitehead, Donnie Wayne [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2007-10-01

    The US is currently on the brink of a nuclear renaissance that will result in near-term construction of new nuclear power plants. In addition, the Department of Energy’s (DOE) ambitious new Global Nuclear Energy Partnership (GNEP) program includes facilities for reprocessing spent nuclear fuel and reactors for transmuting safeguards material. The use of nuclear power and material has inherent safety, security, and safeguards (SSS) concerns that can impact the operation of the facilities. Recent concern over terrorist attacks and nuclear proliferation led to an increased emphasis on security and safeguard issues as well as the more traditional safety emphasis. To meet both domestic and international requirements, nuclear facilities include specific SSS measures that are identified and evaluated through the use of detailed analysis techniques. In the past, these individual assessments have not been integrated, which led to inefficient and costly design and operational requirements. This report provides a framework for a new paradigm where safety, operations, security, and safeguards (SOSS) are integrated into the design and operation of a new facility to decrease cost and increase effectiveness. Although the focus of this framework is on new nuclear facilities, most of the concepts could be applied to any new, high-risk facility.

  11. Towards the development of a scientifically accountable, comprehensive and integrated national road traffic safety databank in South Africa

    CSIR Research Space (South Africa)

    Mynhardt, DC

    2014-07-01

    Full Text Available Transport Conference, CSIR Convention Centre, Pretoria, 7-10 July 2014 Towards the development of a scientifically accountable, comprehensive and integrated national road traffic safety databank in South Africa D. C. MYNHARDT Council for Scientific...

  12. Using Groupware to Gather and Analyze Intelligence in a Public Setting: Development of Integral Safety Plans in an Electronic Meeting

    NARCIS (Netherlands)

    Rouwette, E.A.J.A.; Vennix, J.A.M.; Vriens, D.J.

    2003-01-01

    This chapter focuses on the use of groupware to support local governments in activities in the intelligence cycle. Local governments in The Netherlands have a central role in developing integral safety plans for their district. However, in the implementation of safety plans the contribution of

  13. Integral test facilities for validation of the performance of passive safety systems and natural circulation

    International Nuclear Information System (INIS)

    Choi, J. H.

    2010-10-01

    Passive safety systems are becoming an important component in advanced reactor designs. This has led to an international interest in examining natural circulation phenomena as this may play an important role in the operation of these passive safety systems. Understanding reactor system behaviour is a challenging process due to the complex interactions between components and associated phenomena. Properly scaled integral test facilities can be used to explore these complex interactions. In addition, system analysis computer codes can be used as predictive tools in understanding the complex reactor system behaviour. However, before the application of system analysis computer codes for reactor design, it is capability in making predictions needs to be validated against the experimental data from a properly scaled integral test facility. The IAEA has organized a coordinated research project (CRP) on natural circulation phenomena, modeling and reliability of passive systems that utilize natural circulation. This paper is a part of research results from this CRP and describes representative international integral test facilities that can be used for data collection for reactor types in which natural circulation may play an important role. Example experiments were described along with the analyses of these example cases in order to examine the ability of system codes to model the phenomena that are occurring in the test facilities. (Author)

  14. A status report on the integral fast reactor fuels and safety program

    International Nuclear Information System (INIS)

    Pedersen, D.R.; Seidel, B.R.

    1990-01-01

    The integral fast reactor (IFR) is an advanced liquid-metal-cooled reactor (ALMR) concept being developed at Argonne National Laboratory. The IFR program is specifically responsible for the irradiation performance, advanced core design, safety analysis, and development of the fuel cycle for the US Department of Energy's ALMR program. The basic elements of the IFR concept are (a) metallic fuel, (b) liquid-sodium cooling, (c) modular, pool-type reactor configuration, (d) an integral fuel cycle based upon pyrometallurgical processing. The most significant safety aspects of the IFR program result from its unique fuel design, a ternary alloy of uranium, plutonium, and zirconium. This fuel is based on experience gained through > 25 yr operation of the Experimental Breeder Reactor II (EBR-II) with a uranium alloy metallic fuel. The ultimate criteria for fuel pin design is the overall integrity at the target burnup. The probability of core meltdown is remote; however, a theoretical possibility of core meltdown remains. The next major step in the IFR development program will be a full-scale pyroprocessing demonstration to be carried out in conjunction with EBR-II. The IFR fuel cycle closure based on pyroprocessing will also have a dramatic impact on waste management options and on actinide recycling

  15. Fluor Daniel Hanford Inc. integrated safety management system phase 1 verification final report

    Energy Technology Data Exchange (ETDEWEB)

    PARSONS, J.E.

    1999-10-28

    The purpose of this review is to verify the adequacy of documentation as submitted to the Approval Authority by Fluor Daniel Hanford, Inc. (FDH). This review is not only a review of the Integrated Safety Management System (ISMS) System Description documentation, but is also a review of the procedures, policies, and manuals of practice used to implement safety management in an environment of organizational restructuring. The FDH ISMS should support the Hanford Strategic Plan (DOE-RL 1996) to safely clean up and manage the site's legacy waste; deploy science and technology while incorporating the ISMS theme to ''Do work safely''; and protect human health and the environment.

  16. River Protection Project Integrated safety management system phase II verification review plan - 7/29/99

    International Nuclear Information System (INIS)

    SHOOP, D.S.

    1999-01-01

    The purpose of this review is to verify the implementation status of the Integrated Safety Management System (ISMS) for the River Protection Project (RPP) facilities managed by Fluor Daniel Hanford, Inc. (FDH) and operated by Lockheed Martin Hanford Company (LMHC). This review will also ascertain whether within RPP facilities and operations the work planning and execution processes are in place and functioning to effectively protect the health and safety of the workers, public, environment, and federal property over the RPP life cycle. The RPP ISMS should support the Hanford Strategic Plan (DOERL-96-92) to safely clean up and manage the site's legacy waste and deploy science and technology while incorporating the ISMS central theme to ''Do work safely'' and protect human health and the environment

  17. Methodology for the Integration of Safety in the Optimization of the Advanced Reactors Design

    International Nuclear Information System (INIS)

    Grinblat, P.; Schlamp, M.; Brasnarof, D.; Gimenez, M.

    2003-01-01

    In this work a new methodology has been developed and implemented for taking into account the safety levels of the reactor in a design optimization process, by using Design Maps.They represent a new technique for comparing critical variables in case an accidental sequenced happened, with limit values set by the design criteria.So a good balance is achieved, without allowing the economic performance search to cause a too risky reactor, and guaranteeing the competitiveness of it in spite of the safety costs.Up to the moment, there is no design tool able to accomplish this task in an integrated way.A computational tool based on this methodology has been implemented.These tool specially programmed routines allow carrying out the mentioned tasks

  18. Environment, Safety, Health, and Quality Plan for the Buried Waste Integrated Demonstration Program

    International Nuclear Information System (INIS)

    Walker, S.

    1994-05-01

    The Buried Waste Integrated Demonstration (BWID) is a program funded by the US Department of Energy Office of Technology Development. BWID supports the applied research, development, demonstration, testing, and evaluation of a suite of advanced technologies that together form a comprehensive remediation system for the effective and efficient remediation of buried waste. This document describes the Environment, Safety, Health, and Quality requirements for conducting BWID activities at the Idaho National Engineering Laboratory. Topics discussed in this report, as they apply to BWID operations, include Federal, State of Idaho, and Environmental Protection Agency regulations, Health and Safety Plans, Quality Program Plans, Data Quality Objectives, and training and job hazard analysis. Finally, a discussion is given on CERCLA criteria and System and Performance audits as they apply to the BWID Program

  19. [Management, quality of health and occupational safety and hospital organization: is integration possible?].

    Science.gov (United States)

    Corrao, Carmela Romana Natalina

    2011-01-01

    The evolution of the national and European legislation has progressively transformed the working environments into organized environments. Specific models for its management are being proposed, which should be integrated into general management strategies. In the case of hospitals this integration should consider the peculiar organizational complexity, where the management of the occupational risk needs to be integrated with clinical risk management and economic risk management. Resources management should also consider that Occupational Medicine has not a direct monetary benefit for the organisation, but only indirect health consequences in terms of reduction of accidents and occupational diseases. The deep and simultaneous analysis of the current general management systems and the current management methods of occupational safety and health protection allows one to hyphotesise a possible integration between them. For both of them the Top Management is the main responsible of the quality management strategies and the use of specific documents in the managerial process, such as the document of risks evaluation in the occupational management and the quality manual in the general management, is of paramount importance. An integrated management has also the scope to pursue a particular kind of quality management, where ethics and job satisfaction are innovative, as established by recent European guidelines, management systems and national legislations.

  20. SAFETY

    CERN Multimedia

    Niels Dupont

    2013-01-01

    CERN Safety rules and Radiation Protection at CMS The CERN Safety rules are defined by the Occupational Health & Safety and Environmental Protection Unit (HSE Unit), CERN’s institutional authority and central Safety organ attached to the Director General. In particular the Radiation Protection group (DGS-RP1) ensures that personnel on the CERN sites and the public are protected from potentially harmful effects of ionising radiation linked to CERN activities. The RP Group fulfils its mandate in collaboration with the CERN departments owning or operating sources of ionising radiation and having the responsibility for Radiation Safety of these sources. The specific responsibilities concerning "Radiation Safety" and "Radiation Protection" are delegated as follows: Radiation Safety is the responsibility of every CERN Department owning radiation sources or using radiation sources put at its disposition. These Departments are in charge of implementing the requi...

  1. An Integrated Approach for Characterization of Uncertainty in Complex Best Estimate Safety Assessment

    International Nuclear Information System (INIS)

    Pourgol-Mohamad, Mohammad; Modarres, Mohammad; Mosleh, Ali

    2013-01-01

    This paper discusses an approach called Integrated Methodology for Thermal-Hydraulics Uncertainty Analysis (IMTHUA) to characterize and integrate a wide range of uncertainties associated with the best estimate models and complex system codes used for nuclear power plant safety analyses. Examples of applications include complex thermal hydraulic and fire analysis codes. In identifying and assessing uncertainties, the proposed methodology treats the complex code as a 'white box', thus explicitly treating internal sub-model uncertainties in addition to the uncertainties related to the inputs to the code. The methodology accounts for uncertainties related to experimental data used to develop such sub-models, and efficiently propagates all uncertainties during best estimate calculations. Uncertainties are formally analyzed and probabilistically treated using a Bayesian inference framework. This comprehensive approach presents the results in a form usable in most other safety analyses such as the probabilistic safety assessment. The code output results are further updated through additional Bayesian inference using any available experimental data, for example from thermal hydraulic integral test facilities. The approach includes provisions to account for uncertainties associated with user-specified options, for example for choices among alternative sub-models, or among several different correlations. Complex time-dependent best-estimate calculations are computationally intense. The paper presents approaches to minimize computational intensity during the uncertainty propagation. Finally, the paper will report effectiveness and practicality of the methodology with two applications to a complex thermal-hydraulics system code as well as a complex fire simulation code. In case of multiple alternative models, several techniques, including dynamic model switching, user-controlled model selection, and model mixing, are discussed. (authors)

  2. Application of the integrated safety assessment methodology to the protection of electric systems

    International Nuclear Information System (INIS)

    Hortal, Javier; Izquierdo, Jose M.

    1996-01-01

    The generalization of classical techniques for risk assessment incorporating dynamic effects is the main objective of the Integrated Safety Assessment Methodology, as practical implementation of Protection Theory. Transient stability, contingency analysis and protection setpoint verification in electric power systems are particularly appropriate domains of application, since the coupling of reliability and dynamic analysis in the protection assessment process is being increasingly demanded. Suitable techniques for dynamic simulation of sequences of switching events in power systems are derived from the use of quasi-linear equation solution algorithms. The application of the methodology, step by step, is illustrated in a simple but representative example

  3. Generic safety evaluation report regarding integrity of BWR scram system piping

    International Nuclear Information System (INIS)

    1981-08-01

    Safety concerns associated with postulated pipe breaks in the boiling water reactor (BWR) scram system were identified during the staff's continuing investigation of the Browns Ferry Unit 3 control rod partial insertion failure on June 28, 1980. This report includes an evaluation of the licensing basis for the BWR scram discharge volume (SDV) piping and an assessment of the potential for the SDV piping to fail while in service. A discussion of the means available for mitigation an unlikely SDV system failure is provided. Generic recommendations are made to improve mitigation capability and ensure that system integrity is maintained in service

  4. SDL-Based Protocol Validation for the Integrated Safety Communication Network in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kim, Jung-hun; Kim, Dong-hoon; Lee, Dong-young; Park, Sung-woo

    2006-01-01

    The communication protocol in nuclear power plants needs to be validated systematically to avoid the critical situation that may be caused by its own faults. We establish the methodology to validate the protocol designed for the Integrated Safety Communication Networks (ISCN) of Korea Nuclear Instrumentation and Control System (KNICS). The ISCN protocol is specified using the formal description technique called the SDL. The validation of ISCN protocol is done via the Simulator and Validator, both of which are main functions provided by the SDL

  5. Integrated Management System in construction company-effective tool of quality, environment and safety level improving

    OpenAIRE

    Gašparík, Jozef

    2009-01-01

    Contribution Presents the struCture of integrated M anageMent systeM ( iMs) according to international standards ISO 9001:2008, ISO 14001:2004 and STN OHSAS 18001:2009, which consists of 3 management systems focused to quality, environment and safety of building processes. The purpose of paper is to describe basic steps concerning the development of IMS. Paper analises basic processes of IMS like company vision, IMS planning, implementing, monitoring, revive and improving. The paper presents ...

  6. Risk management: integration of social and technical risk variables into safety assessments of LWR'S

    International Nuclear Information System (INIS)

    Turnage, J.J.; Husseiny, A.A.

    1980-01-01

    A risk management methodology is developed here to formalize the acceptability levels of commercial LWR power plants via the estimation of risk levels acceptable to the public and the integration of such estimates into risk-benefit analysis. Utility theory is used for developing preference models based on value trade-offs among multiple objectives and uncertainties about the impact of alternatives. The method involves reducing the various variables affecting safety acceptability decisions to a single function that provides a metric for acceptability levels. The function accomondates for technical criteria related to design and licensing decisions, as well as public reactions to certain choices

  7. Major results from safety-related integral effect tests with VISTA-ITL for the SMART design

    International Nuclear Information System (INIS)

    Park, H. S.; Min, B. Y.; Shin, Y. C.; Yi, S. J.

    2012-01-01

    A series of integral effect tests (IETs) was performed by the Korea Atomic Energy Research Inst. (KAERI) using the VISTA integral test loop (VISTA-ITL) as a small-scale IET program. Among them this paper presents major results acquired from the safety-related IETs with the VISTA-ITL facility for the SMART design. Three small-break loss-of-coolant accident (SBLOCA) tests of safety injection system (SIS) line break, shutdown cooling system (SCS) line break and pressurizer safety valve (PSV) line break were successfully performed and the transient characteristics of a complete loss of flowrate (CLOF) was simulated properly with the VISTA-ITL facility. (authors)

  8. Lessons learned in the implementation of Integrated Safety Management at DOE Order Compliance Sites vs Necessary and Sufficient Sites

    International Nuclear Information System (INIS)

    Hill, R.L.

    2000-01-01

    This paper summarizes the development and implementation of Integrated Safety Management (ISM) at an Order Compliance Site (Savannah River Site) and a Necessary and Sufficient Site (Nevada Test Site). A discussion of each core safety function of ISM is followed by an example from an Order Compliance Site and a Necessary and Sufficient Site. The Savannah River Site was the first DOE site to have a DOE Headquarters-validated and approved ISM System. The NTS is beginning the process of verification and validation. This paper defines successful strategies for integrating Environment, Safety, and Health management into work under various scenarios

  9. Application of an integrated PC-based neutronics code system to criticality safety

    International Nuclear Information System (INIS)

    Briggs, J.B.; Nigg, D.W.

    1991-01-01

    An integrated system of neutronics and radiation transport software suitable for operation in an IBM PC-class environment has been under development at the Idaho National Engineering Laboratory (INEL) for the past four years. Four modules within the system are particularly useful for criticality safety applications. Using the neutronics portion of the integrated code system, effective neutron multiplication values (k eff values) have been calculated for a variety of benchmark critical experiments for metal systems (Plutonium and Uranium), Aqueous Systems (Plutonium and Uranium) and LWR fuel rod arrays. A description of the codes and methods used in the analysis and the results of the benchmark critical experiments are presented in this paper. In general, excellent agreement was found between calculated and experimental results. (Author)

  10. US Department of Energy, Richland Operations Office Integrated Safety Management System Program Description

    International Nuclear Information System (INIS)

    SHOOP, D.S.

    2000-01-01

    The purpose of this Integrated Safety Management System (ISMS) Program Description (PD) is to describe the U.S. Department of Energy (DOE), Richland Operations Office (RL) ISMS as implemented through the RL Integrated Management System (RIMS). This PD does not impose additional requirements but rather provides an overview describing how various parts of the ISMS fit together. Specific requirements for each of the core functions and guiding principles are established in other implementing processes, procedures, and program descriptions that comprise RIMS. RL is organized to conduct work through operating contracts; therefore, it is extremely difficult to provide an adequate ISMS description that only addresses RL functions. Of necessity, this PD contains some information on contractor processes and procedures which then require RL approval or oversight

  11. Scenario Development Workshop Synopsis. Integration Group for the Safety Case - June 2015

    International Nuclear Information System (INIS)

    Smith, Paul; Voinis, Sylvie; Griffault, Lise; De Meredieu, Jean; Kwong, Gloria; ); Van Luik, Abraham; Bailey, Lucy; Capouet, Manuel; Depaus, Christophe; Makino, Hitoshi; Leigh, Christi; Kirkes, Ross; Leino, Jaakko; Niemeyer, Matthias; Wolf, Jens; Watson, Sarah; Franke, Bettina; Ilett, Doug; Pastina, Barbara; Weetjens, Eef

    2016-03-01

    Scenario development and selection describes the collection and organisation of the scientific and technical information relevant to the potential paths of evolution of a radioactive waste disposal facility (repository) that is necessary to assess its long-term performance and safety. In 1999, the NEA held its first workshop on scenario development in Madrid, Spain, with the objective to review the methods for developing scenarios in safety assessments and their application. Since then, the process of scenario development and analysis for the disposal of radioactive waste has changed and, in 2015, the NEA Integration Group for the Safety Case (IGSC) held a second workshop on this topic at its offices in Paris to further evaluate the experience acquired in developing scenarios since 1999. To prepare for this workshop, the IGSC also launched a survey in 2014 to gather the latest scenario development and uncertainty management strategies used in IGSC member countries. The purposes of the workshop were to (i) provide a forum to review and discuss methods for scenario development and their contribution to the development of recent safety cases (since the 1999 workshop); (ii) examine the latest methods and compare their scope, consistency and function within the overall safety assessment process, based on practical experience of applications; and (iii) provide a basis for producing the present report summarising the current status of scenario methodologies, identifying where sufficient methods exist and any outstanding problem areas. This report provides an overview of the state of the art in scenario development related to the long-term safety of geological repositories for radioactive waste. In particular, it discusses how potential scenarios are developed in safety assessments of radioactive waste that contains long-lived radionuclides. Safety assessment is the process of quantitatively and qualitatively evaluating the safety of a repository, often in support of a

  12. Safety

    International Nuclear Information System (INIS)

    2001-01-01

    This annual report of the Senior Inspector for the Nuclear Safety, analyses the nuclear safety at EDF for the year 1999 and proposes twelve subjects of consideration to progress. Five technical documents are also provided and discussed concerning the nuclear power plants maintenance and safety (thermal fatigue, vibration fatigue, assisted control and instrumentation of the N4 bearing, 1300 MW reactors containment and time of life of power plants). (A.L.B.)

  13. Integrated Safety Management System Phase 1 and 2 Verification for the Environmental Restoration Contractor Volumes 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    CARTER, R.P.

    2000-04-04

    DOE Policy 450.4 mandates that safety be integrated into all aspects of the management and operations of its facilities. The goal of an institutionalized Integrated Safety Management System (ISMS) is to have a single integrated system that includes Environment, Safety, and Health requirements in the work planning and execution processes to ensure the protection of the worker, public, environment, and the federal property over the life cycle of the Environmental Restoration (ER) Project. The purpose of this Environmental Restoration Contractor (ERC) ISMS Phase MI Verification was to determine whether ISMS programs and processes were institutionalized within the ER Project, whether these programs and processes were implemented, and whether the system had promoted the development of a safety conscious work culture.

  14. 78 FR 10181 - Global Quality Systems-An Integrated Approach To Improving Medical Product Safety; Public Workshop

    Science.gov (United States)

    2013-02-13

    ...] Global Quality Systems--An Integrated Approach To Improving Medical Product Safety; Public Workshop... (AFDO), is announcing a public workshop entitled ``Global Quality Systems--An Integrated Approach to... topics concerning FDA requirements related to the production and marketing of drugs and/or devices...

  15. Monitoring the Long-Term Effectiveness of Integrated Safety Management System (ISMS) Implementation Through Use of a Performance Dashboard Process

    International Nuclear Information System (INIS)

    Kinney, Michael D.; Barrick, William D.

    2008-01-01

    This session will examine a method developed by Federal and Contractor personnel at the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) to examine long-term maintenance of DOE Integrated Safety Management System (ISMS) criteria, including safety culture attributes, as well as identification of process improvement opportunities. This process was initially developed in the summer of 2000 and has since been expanded to recognize the importance of safety culture attributes, and associated safety culture elements, as defined in DOE M 450.4-1, 'Integrated Safety Management System Manual'. This process has proven to significantly enhance collective awareness of the importance of long-term ISMS implementation as well as support commitments by NNSA/NSO personnel to examine the continued effectiveness of ISMS processes

  16. An integrated framework for cost- benefit analysis in road safety projects using AHP method

    Directory of Open Access Journals (Sweden)

    Mahsa Mohamadian

    2011-10-01

    Full Text Available Cost benefit analysis (CBA is a useful tool for investment decision-making from economic point of view. When the decision involves conflicting goals, the multi-attribute analysis approach is more capable; because there are some social and environmental criteria that cannot be valued or monetized by cost benefit analysis. The complex nature of decision-making in road safety normally makes it difficult to reach a single alternative solution that can satisfy all decision-making problems. Generally, the application of multi-attribute analysis in road sector is promising; however, the applications are in preliminary stage. Some multi-attribute analysis techniques, such as analytic hierarchy process (AHP have been widely used in practice. This paper presents an integrated framework with CBA and AHP methods to select proper alternative in road safety projects. The proposed model of this paper is implemented for a case study of improving a road to reduce the accidents in Iran. The framework is used as an aid to cost benefit tool in road safety projects.

  17. Integrated risk reduction framework to improve railway hazardous materials transportation safety.

    Science.gov (United States)

    Liu, Xiang; Saat, M Rapik; Barkan, Christopher P L

    2013-09-15

    Rail transportation plays a critical role to safely and efficiently transport hazardous materials. A number of strategies have been implemented or are being developed to reduce the risk of hazardous materials release from train accidents. Each of these risk reduction strategies has its safety benefit and corresponding implementation cost. However, the cost effectiveness of the integration of different risk reduction strategies is not well understood. Meanwhile, there has been growing interest in the U.S. rail industry and government to best allocate resources for improving hazardous materials transportation safety. This paper presents an optimization model that considers the combination of two types of risk reduction strategies, broken rail prevention and tank car safety design enhancement. A Pareto-optimality technique is used to maximize risk reduction at a given level of investment. The framework presented in this paper can be adapted to address a broader set of risk reduction strategies and is intended to assist decision makers for local, regional and system-wide risk management of rail hazardous materials transportation. Copyright © 2013 Elsevier B.V. All rights reserved.

  18. Integrated assessment of pedestrian head impact protection in testing secondary safety and autonomous emergency braking.

    Science.gov (United States)

    Searson, D J; Anderson, R W G; Hutchinson, T P

    2014-02-01

    Pedestrian impact testing is used to provide information to the public about the relative level of protection provided by different vehicles to a struck pedestrian. Autonomous Emergency Braking (AEB) is a relatively new technology that aims to reduce the impact speed of such crashes. It is expected that vehicles with AEB will pose less harm to pedestrians, and that the benefit will come about through reductions in the number of collisions and a change in the severity of impacts that will still occur. In this paper, an integration of the assessment of AEB performance and impact performance is proposed based on average injury risk. Average injury risk is calculated using the result of an impact test and a previously published distribution of real world crash speeds. A second published speed distribution is used that accounts for the effects of AEB, and reduced average risks are implied. This principle allows the effects of AEB systems and secondary safety performance to be integrated into a single measure of safety. The results are used to examine the effect of AEB on Euro NCAP and ANCAP assessments using previously published results on the likely effect of AEB. The results show that, given certain assumptions about AEB performance, the addition of AEB is approximately the equivalent of increasing Euro NCAP test performance by one band, which corresponds to an increase in the score of 25% of the maximum. Copyright © 2013 Elsevier Ltd. All rights reserved.

  19. Integrating model checking with HiP-HOPS in model-based safety analysis

    International Nuclear Information System (INIS)

    Sharvia, Septavera; Papadopoulos, Yiannis

    2015-01-01

    The ability to perform an effective and robust safety analysis on the design of modern safety–critical systems is crucial. Model-based safety analysis (MBSA) has been introduced in recent years to support the assessment of complex system design by focusing on the system model as the central artefact, and by automating the synthesis and analysis of failure-extended models. Model checking and failure logic synthesis and analysis (FLSA) are two prominent MBSA paradigms. Extensive research has placed emphasis on the development of these techniques, but discussion on their integration remains limited. In this paper, we propose a technique in which model checking and Hierarchically Performed Hazard Origin and Propagation Studies (HiP-HOPS) – an advanced FLSA technique – can be applied synergistically with benefit for the MBSA process. The application of the technique is illustrated through an example of a brake-by-wire system. - Highlights: • We propose technique to integrate HiP-HOPS and model checking. • State machines can be systematically constructed from HiP-HOPS. • The strengths of different MBSA techniques are combined. • Demonstrated through modeling and analysis of brake-by-wire system. • Root cause analysis is automated and system dynamic behaviors analyzed and verified

  20. Do we need an integrative approach to food safety at the country level?

    Energy Technology Data Exchange (ETDEWEB)

    Ristic, G E-mail:risticg@eunet yu [Department of Nutrition, Medical Faculty, Belgrade (Yugoslavia)

    2002-05-01

    Scientific data show increasing evidence of relationship between food safety and food standards on one hand and public health concern on the other hand. In FR Yugoslavia in 1989 the system of reporting on food safety issues on federal and republic level was established. The system provides data on laboratory analysis of 22 food items (bread, milk, meat and meat products, vegetables, processed vegetables etc). Those items were and still are tested on food quality and safety parameters such as microbiological, chemical and radio nuclides. Seldom all required testing on chemical and radio nuclides are performed, so we lack exact risk assessment for those contaminants. Further, during war conflict in FR Yugoslavia and also due to industrial hazards in neighbouring countries (Rumania, Hungary) high quantities of PCBs, dioxins, heavy metals, arsenic compounds and other toxic compounds contaminated the environment. In the soil and in some food products (animal fats predominantly) radionuclides originating from Chernobyl hazard can still be detected. In order to identify the level of exposure to chemical and radio nuclide contaminants in the food chain it is essential to test intensively and systematically food from animal and from plant origin. In order to prevent entering the contaminants to the food chain new recommendations from WHO, FAO and EU suggest implementation of integrative approach to food safety and control over the whole chain of food production from 'farm to table'. This approach provides control of the contaminants in soil, water, air, control over primary food production (covering animal feed too), intensive control over processing with implementation of HACCP system, but also, over transportation, retail trade, street food and home made food too. In our country creation of the map of the polluted areas, and actions in order to treat the pollution should accompany implementation of this new food safety system. The need for assessment of the level of

  1. Do we need an integrative approach to food safety at the country level?

    International Nuclear Information System (INIS)

    Ristic, G.

    2002-01-01

    Scientific data show increasing evidence of relationship between food safety and food standards on one hand and public health concern on the other hand. In FR Yugoslavia in 1989 the system of reporting on food safety issues on federal and republic level was established. The system provides data on laboratory analysis of 22 food items (bread, milk, meat and meat products, vegetables, processed vegetables etc). Those items were and still are tested on food quality and safety parameters such as microbiological, chemical and radio nuclides. Seldom all required testing on chemical and radio nuclides are performed, so we lack exact risk assessment for those contaminants. Further, during war conflict in FR Yugoslavia and also due to industrial hazards in neighbouring countries (Rumania, Hungary) high quantities of PCBs, dioxins, heavy metals, arsenic compounds and other toxic compounds contaminated the environment. In the soil and in some food products (animal fats predominantly) radionuclides originating from Chernobyl hazard can still be detected. In order to identify the level of exposure to chemical and radio nuclide contaminants in the food chain it is essential to test intensively and systematically food from animal and from plant origin. In order to prevent entering the contaminants to the food chain new recommendations from WHO, FAO and EU suggest implementation of integrative approach to food safety and control over the whole chain of food production from 'farm to table'. This approach provides control of the contaminants in soil, water, air, control over primary food production (covering animal feed too), intensive control over processing with implementation of HACCP system, but also, over transportation, retail trade, street food and home made food too. In our country creation of the map of the polluted areas, and actions in order to treat the pollution should accompany implementation of this new food safety system. The need for assessment of the level of

  2. Integrated risk reduction framework to improve railway hazardous materials transportation safety

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-09-15

    Highlights: • An integrated framework is developed to optimize risk reduction. • A negative binomial regression model is developed to analyze accident-cause-specific railcar derailment probability. • A Pareto-optimality technique is applied to determine the lowest risk given any level of resource. • A multi-attribute decision model is developed to determine the optimal amount of investment for risk reduction. • The models could aid the government and rail industry in developing cost-efficient risk reduction policy and practice. -- Abstract: Rail transportation plays a critical role to safely and efficiently transport hazardous materials. A number of strategies have been implemented or are being developed to reduce the risk of hazardous materials release from train accidents. Each of these risk reduction strategies has its safety benefit and corresponding implementation cost. However, the cost effectiveness of the integration of different risk reduction strategies is not well understood. Meanwhile, there has been growing interest in the U.S. rail industry and government to best allocate resources for improving hazardous materials transportation safety. This paper presents an optimization model that considers the combination of two types of risk reduction strategies, broken rail prevention and tank car safety design enhancement. A Pareto-optimality technique is used to maximize risk reduction at a given level of investment. The framework presented in this paper can be adapted to address a broader set of risk reduction strategies and is intended to assist decision makers for local, regional and system-wide risk management of rail hazardous materials transportation.

  3. An integrated safety analysis of intravenous ibuprofen (Caldolor® in adults

    Directory of Open Access Journals (Sweden)

    Southworth SR

    2015-10-01

    Full Text Available Stephen R Southworth,1 Emily J Woodward,2 Alex Peng,2 Amy D Rock21North Mississippi Sports Medicine and Orthopaedic Clinic, PLLC, Tupelo, MS, 2Department of Research and Development, Cumberland Pharmaceuticals Inc., Nashville, TN, USAAbstract: Intravenous (IV nonsteroidal anti-inflammatory drugs such as IV ibuprofen are increasingly used as a component of multimodal pain management in the inpatient and outpatient settings. The safety of IV ibuprofen as assessed in ten sponsored clinical studies is presented in this analysis. Overall, 1,752 adult patients have been included in safety and efficacy trials over 11 years; 1,220 of these patients have received IV ibuprofen and 532 received either placebo or comparator medication. The incidence of adverse events (AEs, serious AEs, and changes in vital signs and clinically significant laboratory parameters have been summarized and compared to patients receiving placebo or active comparator drug. Overall, IV ibuprofen has been well tolerated by hospitalized and outpatient patients when administered both prior to surgery and postoperatively as well as for nonsurgical pain or fever. The overall incidence of AEs is lower in patients receiving IV ibuprofen as compared to those receiving placebo in this integrated analysis. Specific analysis of hematological and renal effects showed no increased risk for patients receiving IV ibuprofen. A subset analysis of elderly patients suggests that no dose adjustment is needed in this higher risk population. This integrated safety analysis demonstrates that IV ibuprofen can be safely administered prior to surgery and continued in the postoperative period as a component of multimodal pain management.Keywords: NSAID, surgical pain, fever, perioperative analgesia, critical care, multimodal pain management

  4. Route Assessment for Unmanned Aerial Vehicle Based on Cloud Model

    Directory of Open Access Journals (Sweden)

    Xixia Sun

    2014-01-01

    Full Text Available An integrated route assessment approach based on cloud model is proposed in this paper, where various sources of uncertainties are well kept and modeled by cloud theory. Firstly, a systemic criteria framework incorporating models for scoring subcriteria is developed. Then, the cloud model is introduced to represent linguistic variables, and survivability probability histogram of each route is converted into normal clouds by cloud transformation, enabling both randomness and fuzziness in the assessment environment to be managed simultaneously. Finally, a new way to measure the similarity between two normal clouds satisfying reflexivity, symmetry, transitivity, and overlapping is proposed. Experimental results demonstrate that the proposed route assessment approach outperforms fuzzy logic based assessment approach with regard to feasibility, reliability, and consistency with human thinking.

  5. Integrating Safety and Security in the EU: Past developments and suggested ways forward

    International Nuclear Information System (INIS)

    Rossi, Loris

    2016-01-01

    The Framework provided by the UN Model Regulation for the Transport of Dangerous Goods is the core of the legislation on transport of radioactive material (and all classes of dangerous goods) in the EU. This has resulted in European agreements ADR, RID and ADN for international transport as well as a single directive for land transport within the EU. In addition the EU has adopted a range of directives and regulations dealing specifically with several aspects of safety of nuclear and radioactive material. While the overall safety framework is now well developed and fairly stable, a security framework is evolving, based on the IAEA recommendations. In the EU, several initiatives such as the CBRN action plan and the review of the application of telematics for the transport of dangerous goods will most likely result in more developments coming on stream in the near future. This suggests that an integrated approach would be beneficial to avoid divergent developments and to keep track of new developments in an orderly fashion. An integrated approach for a safe and secure supply chain for radioactive material is proposed. The framework for a supply chain can be built around the extensive corpus of legislation/recommendations and concepts that are already existing (such as the “Known Consignor” in the framework of the EU aviation security or the “Authorised Economic Operator” in the EU Community Custom Code). This would allow for the need to maintain control of the numerous proposals that are taking place. Advantages and drawbacks are outlined. More generally, the development of an integrated safe and secure supply chain would bring clarity and transparency to the overall system of provisions for a safe and secure management of radioactive material. (author)

  6. Report of study group 4.3 ''pipeline integrity management and safety''

    Energy Technology Data Exchange (ETDEWEB)

    Clavel, P.

    2000-07-01

    This report highlights the Pipeline integrity Management methods being implemented by gas companies. These aim at maintaining the current high safety level, prevent major hazards, ensure the integrity of the pipeline and protect people and environment in the vicinity of the pipeline in the most cost effective way. It should be noticed that Pipeline Integrity Management aspects, technical and organisational, are included in the more general framework of the Safety Management System. Currently, more and more gas companies implement such a system on the basis of standards like ISO 9000 and so on. In this way, the report shows how practices of Pipeline Integrity Management are continually developing in order to adapt to their environment, and to improve performance. Past experience and imminent developments show that Pipeline Integrity Management is a flexible and efficient approach to improve safety in the long term. Consequently, Pipeline Integrity Management Systems are, under the control of authorities, the best alternative to additional safety regulations. Within the context of deregulation of the European markets and globalization Pipeline Integrity Management appears to be a tool to promote the gas industry in the eyes of the authorities, the market regulators and the customers (industrialists,...). (author)

  7. Integration of radiation protection in occupational health and safety managementsystems - legal requirements and practical realization at the example of the Fraunhofer occupational health and safety management system FRAM

    International Nuclear Information System (INIS)

    Lambotte, S.; Severitt, S.; Weber, U.

    2002-01-01

    The protection of the employees, the people and the environment for the effects of radiation is regulated by numerous laws and rules set by the government and the occupational accident insurances. Primarily these rules apply for the responsibles, normally the employer, as well as for the safety officers. Occupational safety management systems can support these people to carry out their tasks and responsibilities effectively. Also, a systematic handling of the organisation secures that the numerous duties of documentation, time-checking of the proof-lists and dates are respected. Further more, the legal certainty for the responsibles and safety officers will be raised and the occupational, environment, radiation and health protection will be promoted. At the example of the Fraunhofer occupational safety management system (FrAM) it is demonstrated, how radiation protection (ionizing radiation) can be integrated in a progressive intranet supported management system. (orig.)

  8. Assessment of Integrated Pedestrian Protection Systems with Autonomous Emergency Braking (AEB) and Passive Safety Components.

    Science.gov (United States)

    Edwards, Mervyn; Nathanson, Andrew; Carroll, Jolyon; Wisch, Marcus; Zander, Oliver; Lubbe, Nils

    2015-01-01

    Autonomous emergency braking (AEB) systems fitted to cars for pedestrians have been predicted to offer substantial benefit. On this basis, consumer rating programs-for example, the European New Car Assessment Programme (Euro NCAP)-are developing rating schemes to encourage fitment of these systems. One of the questions that needs to be answered to do this fully is how the assessment of the speed reduction offered by the AEB is integrated with the current assessment of the passive safety for mitigation of pedestrian injury. Ideally, this should be done on a benefit-related basis. The objective of this research was to develop a benefit-based methodology for assessment of integrated pedestrian protection systems with AEB and passive safety components. The method should include weighting procedures to ensure that it represents injury patterns from accident data and replicates an independently estimated benefit of AEB. A methodology has been developed to calculate the expected societal cost of pedestrian injuries, assuming that all pedestrians in the target population (i.e., pedestrians impacted by the front of a passenger car) are impacted by the car being assessed, taking into account the impact speed reduction offered by the car's AEB (if fitted) and the passive safety protection offered by the car's frontal structure. For rating purposes, the cost for the assessed car is normalized by comparing it to the cost calculated for a reference car. The speed reductions measured in AEB tests are used to determine the speed at which each pedestrian in the target population will be impacted. Injury probabilities for each impact are then calculated using the results from Euro NCAP pedestrian impactor tests and injury risk curves. These injury probabilities are converted into cost using "harm"-type costs for the body regions tested. These costs are weighted and summed. Weighting factors were determined using accident data from Germany and Great Britain and an independently

  9. A solar vehicle based on sustainable design concept

    Energy Technology Data Exchange (ETDEWEB)

    Taha, Z.; Sah, J.M.; Passarella, R.; Ghazilla, R.A.R.; Ahmad, N.; Jen, Y.H.; Khai, T.T.; Kassim, Z.; Hasanuddin, I.; Yunus, M. [Malaya Univ., Kuala Lumpur (Malaysia). Faculty of Engineering, Centre for Product Design and Manufacture

    2009-07-01

    This paper described a newly constructed solar vehicle that was built specifically for the 2009 World Solar Challenge (WSC) using off-the-shelf parts. Researchers at the Centre for Product Design and Manufacture at the University of Malaya designed and built the solar car which uses solar energy to charge its batteries. Although the total investment for this sustainable product concept is small compared to other solar vehicles, the car's performance has met expectations. Most of the electrical and mechanical parts can be recycled and reused after the WSC event. The photovoltaic (PV) and maximum power point trackers (MPPT) can be re-used for home applications. The DC motor and the controller can be attached to a bicycle and the aluminium parts which make-up the main body structure can be recycled. The design will result in nearly zero waste. The study showed that the process of combining mechanical and electrical components is not an easy task, particularly at the design stage because of the specific characteristics and functions of the individual parts. This paper described how readily available, off-the-shelf mechanical and electrical components were integrated for the solar vehicle. The conceptual design and the performance of the prototype were also presented. 11 refs., 5 tabs., 11 figs.

  10. Ontology-supported research on vaccine efficacy, safety and integrative biological networks.

    Science.gov (United States)

    He, Yongqun

    2014-07-01

    While vaccine efficacy and safety research has dramatically progressed with the methods of in silico prediction and data mining, many challenges still exist. A formal ontology is a human- and computer-interpretable set of terms and relations that represent entities in a specific domain and how these terms relate to each other. Several community-based ontologies (including Vaccine Ontology, Ontology of Adverse Events and Ontology of Vaccine Adverse Events) have been developed to support vaccine and adverse event representation, classification, data integration, literature mining of host-vaccine interaction networks, and analysis of vaccine adverse events. The author further proposes minimal vaccine information standards and their ontology representations, ontology-based linked open vaccine data and meta-analysis, an integrative One Network ('OneNet') Theory of Life, and ontology-based approaches to study and apply the OneNet theory. In the Big Data era, these proposed strategies provide a novel framework for advanced data integration and analysis of fundamental biological networks including vaccine immune mechanisms.

  11. Safety Analysis for PHTS Integrity by the failure of the IHTS function in PGSFR

    Energy Technology Data Exchange (ETDEWEB)

    Ahn, Sang-Jun; Chang, Won-Pyo; Ha, Kwi-Seok; Kang, Seok Hun; Choi, Chi-Woong; Lee, Kwi Lim; Lee, Seung Won; Jeong, Jae-Ho; Kim, Jin Su; Jeong, Taekyeong [KAERI, Daejeon (Korea, Republic of)

    2016-05-15

    In this paper, the failure of the heat removal function of the IHTS by the SWR event is assumed. The integrity of the PHTS is analyzed by MARS-LMR code. A sodium is used as a reactor coolant to transfer the core heat to the turbine. It rigorously reacts with a water or steam in chemical and generates the high pressure waves and high temperature reaction heat. While it has an excellent characteristics as a coolant, there is an event to be necessarily considered in the sodium cooled fast reactor design. The Sodium-Water Reaction(SWR) event can be occurred due to the rupture of steam generator tubes. This event threaten the integrity of the Primary Heat Transfer System(PHTS). It is categorized to the loss of heat sink events, which are undercooling the Primary Heat Transfer System(PHTS). In PGSFR, the SWR event can be occurred in the SG. The PHTS is analyzed to the respects of the integrity of the fuel and cladding using the MARS-LMR code. From the analysis results, the peak temperature of the fuel and cladding have a sufficient margin to the safety acceptance criteria 1,237 .deg. C and 1,075 .deg. C, respectively.

  12. Verkeersveiligheid in Nederland.Nationaal overzicht ten behoeve van de OECD-group S1 on Concepts and Methodologies for Integrated Safety Programmes.

    NARCIS (Netherlands)

    Paar, H.G.

    1983-01-01

    Since 1974 traffic safety policy in the Netherlands has been coordinated by one department of the national government. For research on traffic safety there is a central integrating institute, the Dutch institute for road safety research SWOV. In 1975 a management policy for traffic safety was

  13. Integrated Management System Incorporating Quality Management and Management of Environment, Health and Occupational Safety

    International Nuclear Information System (INIS)

    Manchev, B.; Nenkova, B.; Tomov, E.

    2012-01-01

    Risk Engineering Ltd is a Bulgarian private company founded in 1990 to provide engineering and consulting services applicable to each and every field of the energy sector. Since its establishment Risk Engineering Ltd develops, implement and apply a System for quality assurance, certified for the first time by BVQI (now Bureau Veritas Certification) in 1999 for conformity with the standard ISO 9001:1994. Later on, in connection with the revision of the standards of ISO 9000 series and introduction of the standard ISO 9001:2000 a Quality Management System in conformity with the standard ISO 9001:2000 was developed, introduced and certified. At present, Risk Engineering Ltd has got developed, documented, introduced and certified by Lloyd's Register Quality Assurance (LRQA) Quality Management System in compliance with ISO 9001:2008 on the process approach basis. On this basis and including the requirements of the ISO 14001:2004 (regarding the environment) and OHSAS 18001:2007 (regarding the health and occupational safety), Risk Engineering Ltd has developed and introduced Integrated Management System aim at achieving and demonstrating good results regarding protection of the environment, health and occupational safety. The processes under control by the Integrated Management System and applicable at the company are divided in two general types: A) Management processes: Strategic management and Management of the human resources. B) Processes describing the main activities: design/development process; project management; management of industrial projects and technical infrastructure project; construction, installation, repair and operation of power industry facilities; commercial activities and marketing; investigation of energy efficiency of industrial systems and certification of buildings regarding energy efficiency; consulting activity in the field of industry and energy as well as consultant in accordance with the Law of the Spatial Planning; management of the

  14. Steam generator collector integrity of WWER-1000 reactors. IAEA extrabudgetary programme on the safety of WWER NPPs

    Energy Technology Data Exchange (ETDEWEB)

    Lin, C.; Strupczewski, A. [International Atomic Energy Agency, Vienna (Austria)

    1995-12-31

    At the Consultants` Meeting on `The Safety of WWER-1000 Model 320 Nuclear Power Plants` organized by the IAEA within the framework of its Extrabudgetary Programme on the Safety of WWER-1000 NPPs, which was held in Vienna, 1-5 June 1992, the problem of WWER-1000 steam generator integrity was identified as an important issue of safety concern. Considering the safety importance of this issue, a Consultants` Meeting on `The Steam Generator Integrity of WWER-1000 Nuclear Power Plants` was convened in Vienna in May 1993, attended by 15 international experts in the area to compile information on the steam generator operating experience, deficiencies and corrective measures implemented and planned. In order to also include information from the main designer OKB Gidropress and to finalize the meeting report the IAEA convened a second meeting on the issue on 23-27 November 1993. The present paper summarizes the information and conclusions from those meetings.

  15. Steam generator collector integrity of WWER-1000 reactors. IAEA extrabudgetary programme on the safety of WWER NPPs

    Energy Technology Data Exchange (ETDEWEB)

    Lin, C; Strupczewski, A [International Atomic Energy Agency, Vienna (Austria)

    1996-12-31

    At the Consultants` Meeting on `The Safety of WWER-1000 Model 320 Nuclear Power Plants` organized by the IAEA within the framework of its Extrabudgetary Programme on the Safety of WWER-1000 NPPs, which was held in Vienna, 1-5 June 1992, the problem of WWER-1000 steam generator integrity was identified as an important issue of safety concern. Considering the safety importance of this issue, a Consultants` Meeting on `The Steam Generator Integrity of WWER-1000 Nuclear Power Plants` was convened in Vienna in May 1993, attended by 15 international experts in the area to compile information on the steam generator operating experience, deficiencies and corrective measures implemented and planned. In order to also include information from the main designer OKB Gidropress and to finalize the meeting report the IAEA convened a second meeting on the issue on 23-27 November 1993. The present paper summarizes the information and conclusions from those meetings.

  16. An Integrated Intervention for Increasing Clinical Nurses’ Knowledge of HIV/AIDS-Related Occupational Safety

    Directory of Open Access Journals (Sweden)

    Liping He

    2016-11-01

    Full Text Available Background: Approximately 35 new HIV (Human Immunodeficiency Virus, HIV cases and at least 1000 serious infections are transmitted annually to health care workers. In China, HIV prevalence is increasing and nursing personnel are encountering these individuals more than in the past. Contaminated needle-stick injuries represent a significant occupational burden for nurses. Evidence suggests that nurses in China may not fully understand HIV/AIDS (Acquired immunodeficiency syndrome, AIDS and HIV-related occupational safety. At this time, universal protection precautions are not strictly implemented in Chinese hospitals. Lack of training may place nurses at risk for occupational exposure to blood-borne pathogens. Objectives: To assess the effectiveness of integrated interventions on nurses’ knowledge improvement about reducing the risk of occupationally acquired HIV infection. Methods: We audited integrated interventions using 300 questionnaires collected from nurses at the Affiliated Hospital of Xiangnan University, a public polyclinic in Hunan Province. The intervention studied was multifaceted and included appropriate and targeted training content for hospital, department and individual levels. After three months of occupational safety integrated interventions, 234 participants who completed the program were assessed. Results: Of the subjects studied, 94.3% (283/300 were injured one or more times by medical sharp instruments or splashed by body fluids in the last year and 95.3% considered their risk of occupational exposure high or very high. After the intervention, awareness of HIV/AIDS-related knowledge improved significantly (χ2 = 86.34, p = 0.00, and correct answers increased from 67.9% to 82.34%. Correct answers regarding risk perception were significantly different between pre-test (54.4% and post-test (66.6% (χ2 = 73.2, p = 0.00. When coming into contact with patient body fluids and blood only 24.0% of subjects used gloves regularly

  17. Generation of integral experiment covariance data and their impact on criticality safety validation

    Energy Technology Data Exchange (ETDEWEB)

    Stuke, Maik; Peters, Elisabeth; Sommer, Fabian

    2016-11-15

    The quantification of statistical dependencies in data of critical experiments and how to account for them properly in validation procedures has been discussed in the literature by various groups. However, these subjects are still an active topic in the Expert Group on Uncertainty Analysis for Criticality Safety Assessment (UACSA) of the OECDNEA Nuclear Science Committee. The latter compiles and publishes the freely available experimental data collection, the International Handbook of Evaluated Criticality Safety Benchmark Experiments, ICSBEP. Most of the experiments were performed as series and share parts of experimental setups, consequently leading to correlation effects in the results. The correct consideration of correlated data seems to be inevitable if the experimental data in a validation procedure is limited or one cannot rely on a sufficient number of uncorrelated data sets, e.g. from different laboratories using different setups. The general determination of correlations and the underlying covariance data as well as the consideration of them in a validation procedure is the focus of the following work. We discuss and demonstrate possible effects on calculated k{sub eff}'s, their uncertainties, and the corresponding covariance matrices due to interpretation of evaluated experimental data and its translation into calculation models. The work shows effects of various modeling approaches, varying distribution functions of parameters and compares and discusses results from the applied Monte-Carlo sampling method with available data on correlations. Our findings indicate that for the reliable determination of integral experimental covariance matrices or the correlation coefficients a detailed study of the underlying experimental data, the modeling approach and assumptions made, and the resulting sensitivity analysis seems to be inevitable. Further, a Bayesian method is discussed to include integral experimental covariance data when estimating an

  18. Generation of integral experiment covariance data and their impact on criticality safety validation

    International Nuclear Information System (INIS)

    Stuke, Maik; Peters, Elisabeth; Sommer, Fabian

    2016-11-01

    The quantification of statistical dependencies in data of critical experiments and how to account for them properly in validation procedures has been discussed in the literature by various groups. However, these subjects are still an active topic in the Expert Group on Uncertainty Analysis for Criticality Safety Assessment (UACSA) of the OECDNEA Nuclear Science Committee. The latter compiles and publishes the freely available experimental data collection, the International Handbook of Evaluated Criticality Safety Benchmark Experiments, ICSBEP. Most of the experiments were performed as series and share parts of experimental setups, consequently leading to correlation effects in the results. The correct consideration of correlated data seems to be inevitable if the experimental data in a validation procedure is limited or one cannot rely on a sufficient number of uncorrelated data sets, e.g. from different laboratories using different setups. The general determination of correlations and the underlying covariance data as well as the consideration of them in a validation procedure is the focus of the following work. We discuss and demonstrate possible effects on calculated k eff 's, their uncertainties, and the corresponding covariance matrices due to interpretation of evaluated experimental data and its translation into calculation models. The work shows effects of various modeling approaches, varying distribution functions of parameters and compares and discusses results from the applied Monte-Carlo sampling method with available data on correlations. Our findings indicate that for the reliable determination of integral experimental covariance matrices or the correlation coefficients a detailed study of the underlying experimental data, the modeling approach and assumptions made, and the resulting sensitivity analysis seems to be inevitable. Further, a Bayesian method is discussed to include integral experimental covariance data when estimating an application

  19. Application of Framework for Integrating Safety, Security and Safeguards (3Ss) into the Design Of Used Nuclear Fuel Storage Facility

    Energy Technology Data Exchange (ETDEWEB)

    Badwan, Faris M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Demuth, Scott F [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-01-06

    Department of Energy’s Office of Nuclear Energy, Fuel Cycle Research and Development develops options to the current commercial fuel cycle management strategy to enable the safe, secure, economic, and sustainable expansion of nuclear energy while minimizing proliferation risks by conducting research and development focused on used nuclear fuel recycling and waste management to meet U.S. needs. Used nuclear fuel is currently stored onsite in either wet pools or in dry storage systems, with disposal envisioned in interim storage facility and, ultimately, in a deep-mined geologic repository. The safe management and disposition of used nuclear fuel and/or nuclear waste is a fundamental aspect of any nuclear fuel cycle. Integrating safety, security, and safeguards (3Ss) fully in the early stages of the design process for a new nuclear facility has the potential to effectively minimize safety, proliferation, and security risks. The 3Ss integration framework could become the new national and international norm and the standard process for designing future nuclear facilities. The purpose of this report is to develop a framework for integrating the safety, security and safeguards concept into the design of Used Nuclear Fuel Storage Facility (UNFSF). The primary focus is on integration of safeguards and security into the UNFSF based on the existing Nuclear Regulatory Commission (NRC) approach to addressing the safety/security interface (10 CFR 73.58 and Regulatory Guide 5.73) for nuclear power plants. The methodology used for adaptation of the NRC safety/security interface will be used as the basis for development of the safeguards /security interface and later will be used as the basis for development of safety and safeguards interface. Then this will complete the integration cycle of safety, security, and safeguards. The overall methodology for integration of 3Ss will be proposed, but only the integration of safeguards and security will be applied to the design of the

  20. DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 1 of 2: Technical standard

    International Nuclear Information System (INIS)

    1998-05-01

    This Department of Energy (DOE) technical standard (referred to as the Standard) provides guidance for integrating and enhancing worker, public, and environmental protection during facility disposition activities. It provides environment, safety, and health (ES and H) guidance to supplement the project management requirements and associated guidelines contained within DOE O 430.1A, Life-Cycle Asset Management (LCAM), and amplified within the corresponding implementation guides. In addition, the Standard is designed to support an Integrated Safety Management System (ISMS), consistent with the guiding principles and core functions contained in DOE P 450.4, Safety Management System Policy, and discussed in DOE G 450.4-1, Integrated Safety Management System Guide. The ISMS guiding principles represent the fundamental policies that guide the safe accomplishment of work and include: (1) line management responsibility for safety; (2) clear roles and responsibilities; (3) competence commensurate with responsibilities; (4) balanced priorities; (5) identification of safety standards and requirements; (6) hazard controls tailored to work being performed; and (7) operations authorization. This Standard specifically addresses the implementation of the above ISMS principles four through seven, as applied to facility disposition activities

  1. Do we see how they perceive risk? An integrated analysis of risk perception and its effect on workplace safety behavior.

    Science.gov (United States)

    Xia, Nini; Wang, Xueqing; Griffin, Mark A; Wu, Chunlin; Liu, Bingsheng

    2017-09-01

    While risk perception is a key factor influencing safety behavior, the academia lacks specific attention to the ways that workers perceive risk, and thus little is known about the mechanisms through which different risk perceptions influence safety behavior. Most previous research in the workplace safety domain argues that people tend to perceive risk based on rational formulations of risk criticality. However, individuals' emotions can be also useful in understanding their perceptions. Therefore, this research employs an integrated analysis concerning the rational and emotional perspectives. Specifically, it was expected that the identified three rational ways of perceiving risk, i.e., perceived probability, severity, and negative utility, would influence the direct emotional risk perception. Furthermore, these four risk perceptions were all expected to positively but differently influence safety behavior. The hypotheses were tested using a sample of 120 construction workers. It was found that all the three rational risk perceptions significantly influenced workers' direct perception of risk that is mainly based on emotions. Furthermore, safety behavior among workers relied mainly on emotional perception but not rational calculations of risk. This research contributes to workplace safety research by highlighting the importance of integrating the emotional assessment of risk, especially when workers' risk perception and behavior are concerned. Suggested avenues for improving safety behavior through improvement in risk perception include being aware of the possibility of different ways of perceiving risk, promoting experience sharing and accident simulation, and uncovering risk information. Copyright © 2017 Elsevier Ltd. All rights reserved.

  2. Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC).

    Energy Technology Data Exchange (ETDEWEB)

    Schultz, Peter Andrew

    2011-12-01

    The objective of the U.S. Department of Energy Office of Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC) is to provide an integrated suite of computational modeling and simulation (M&S) capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive-waste storage facility or disposal repository. Achieving the objective of modeling the performance of a disposal scenario requires describing processes involved in waste form degradation and radionuclide release at the subcontinuum scale, beginning with mechanistic descriptions of chemical reactions and chemical kinetics at the atomic scale, and upscaling into effective, validated constitutive models for input to high-fidelity continuum scale codes for coupled multiphysics simulations of release and transport. Verification and validation (V&V) is required throughout the system to establish evidence-based metrics for the level of confidence in M&S codes and capabilities, including at the subcontiunuum scale and the constitutive models they inform or generate. This Report outlines the nature of the V&V challenge at the subcontinuum scale, an approach to incorporate V&V concepts into subcontinuum scale modeling and simulation (M&S), and a plan to incrementally incorporate effective V&V into subcontinuum scale M&S destined for use in the NEAMS Waste IPSC work flow to meet requirements of quantitative confidence in the constitutive models informed by subcontinuum scale phenomena.

  3. Improving safety through an integrated approach for advanced control room development

    International Nuclear Information System (INIS)

    Haugset, K.; Berg, O.; Foerdestroemmen, N.T.; Kvalem, J.; Nelson, W.R.

    1990-01-01

    With the fast development of computer technology, the potential exists for improving operational safety of nuclear plants by using advanced operator tools in the control room. Specific systems are being introduced, such as systems for alarm handling, failure detection, disturbance diagnosis, procedural advice and others, often based on process modeling techniques or expert system technology. To ensure a maximum benefit from the new technology, a careful integration of the various systems must, however, take place, resulting in a well coordinated interface between the operator and the process. The OECD Halden Reactor Project has started the development of an Integrated Surveillance And Control System (ISACS). The basis for the activity is the experience at Halden in developing specific Computerized Operator Support Systems (COSSs), and the activity around the experimental control room HAMMLAB where detailed validations of operator tools have been performed for a number of years. The first goal in the ISACS project is to have a first, limited prototype in operation at the end of 1990. Validation experiments will follow

  4. Improving safety through an integrated approach for advanced control room development

    International Nuclear Information System (INIS)

    Haugset, K.; Berg, O.; Bologna, S.; Foerdestroemmen, N.T.; Kvalem, J.; Nelson, W.R.; Yamane, N.

    1992-01-01

    With the fast development of computer technology, the potential exists for improving operational safety of nuclear plants by using advanced operator tools in the control room. Specific systems are being introduced, such as systems for alarm handling, failure detection, disturbance diagnosis, procedural advice and others, often based on process modeling techniques or expert system technology. To ensure a maximum benefit from the new technology, a careful integration of the various systems must, however, take place, resulting in a well coordinated interface between the operator and the process. The OECD Halden Reactor Project has started the development of an Integrated Surveillance And Control System (ISACS). The basis for the activity is the experience at Halden in developing specific Computerized Operator Support Systems (COSSs), and the activity around the experimental control room HAMMLAB where detailed validations of operator tools have been performed for a number of years. The first goal in the ISACS project is to have a first, limited prototype in operation at the end of 1990. Validation experiments will follow. (orig.)

  5. Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC)

    International Nuclear Information System (INIS)

    Schultz, Peter Andrew

    2011-01-01

    The objective of the U.S. Department of Energy Office of Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC) is to provide an integrated suite of computational modeling and simulation (M and S) capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive-waste storage facility or disposal repository. Achieving the objective of modeling the performance of a disposal scenario requires describing processes involved in waste form degradation and radionuclide release at the subcontinuum scale, beginning with mechanistic descriptions of chemical reactions and chemical kinetics at the atomic scale, and upscaling into effective, validated constitutive models for input to high-fidelity continuum scale codes for coupled multiphysics simulations of release and transport. Verification and validation (V and V) is required throughout the system to establish evidence-based metrics for the level of confidence in M and S codes and capabilities, including at the subcontiunuum scale and the constitutive models they inform or generate. This Report outlines the nature of the V and V challenge at the subcontinuum scale, an approach to incorporate V and V concepts into subcontinuum scale modeling and simulation (M and S), and a plan to incrementally incorporate effective V and V into subcontinuum scale M and S destined for use in the NEAMS Waste IPSC work flow to meet requirements of quantitative confidence in the constitutive models informed by subcontinuum scale phenomena.

  6. FUNMIG Integrated Project results and conclusions from a safety case perspective

    International Nuclear Information System (INIS)

    Schwyn, B.; Wersin, P.; Rüedi, J.; Schneider, J.; Altmann, S.; Missana, T.; Noseck, U.

    2012-01-01

    The scope of the FUNMIG Integrated Project (IP) was to improve the knowledge base on biogeochemical processes in the geosphere which are relevant for the safety of radioactive waste repositories. An important part of this project involved the interaction between data producers (research) and data users (radioactive waste management organisations in Europe). The aim thereof was to foster the benefits of the research work for performance assessment (PA), and in a broader sense, for the safety case of radioactive waste repositories. For this purpose a specifically adapted procedure was elaborated. Thus, relevant features, events and processes (FEPs) for the three host rock types, clay, crystalline and salt, were taken from internationally accepted catalogues and mapped onto each of the 108 research tasks conducted during the FUNMIG project by a standardised procedure. The main outcome thereof was a host-rock specific tool (Task Evaluation Table) in which the relevance and benefits of the research results were evaluated both from the PA and research perspective. Virtually all generated data within FUNMIG are related to the safety-relevant FEP-groups “transport mechanisms” and “retardation”. Generally speaking, much of the work within FUNMIG helped to support and to increase confidence in the simplified PA transport and retardation models used for calculating radionuclide (RN) transport through the host rock. Some of the studies on retardation processes (e.g. coupled sorption-redox processes at the mineral–water interface) yielded valuable data for all three rock types dealt within the IP. However, most of the studies provided improved insight regarding host-rock specific features and processes, the majority of this work being dedicated to clay-rich and crystalline host rocks. For both of these host rock types, FUNMIG has significantly contributed to improving understanding on a conceptual level, both by providing new experimental data at different spatial

  7. Dynamic dune management, integrating objectives of nature development and coastal safety: Examples from the Netherlands

    Science.gov (United States)

    Arens, Sebastiaan M.; Mulder, Jan P. M.; Slings, Quirinus L.; Geelen, Luc H. W. T.; Damsma, Petra

    2013-10-01

    This paper discusses and compares results of management interventions to remobilise dunes and obtain more autonomous changes in foredunes resulting from a change in coastal defence policy. In recent decades, nature conservation managers tried to restore aeolian dynamics and dune mobility landward of foredunes to maintain threatened, rare pioneer species. Results indicate that destabilisation activities yielded an important increase of blowing sand and its effects on ecology but with a limited effect on the desired integral remobilization of dunes. Roots remaining in the sand after removal of vegetation and soil is one of the main problems. Follow up removal of roots for 3 to 5 years seems to be essential, but it is not clear whether the dunes will remain mobile in the long term. In 1990 the Dutch government decided to maintain the position of the coastline by artificial sand nourishment. An intensive management of the foredunes was no longer required. Consequently, natural processes in the foredunes revived, and the sediment budget of the beach-dune system changed. Two main types of responses are visible. In some areas, increased input of sand resulted in the development of embryonic dunes seaward of the former foredunes, leading to increased stabilisation of the former foredunes. In other areas, development of embryonic dunes was insignificant despite the increased sand input, but wind erosion features developed in the foredunes, and the environment was more dynamic. The reasons for the differences are not clear, and the interaction between shoreface, beach and dunes is still poorly understood. Until now, attempts to mobilise the inner dunes were independent of changes made to the foredunes. We argue that an integrated, dynamic approach to coastal management, taking account of all relevant functions (including safety and natural values) and the dune-beach system as a whole, may provide new and durable solutions. An integrated approach would ideally provide fresh

  8. 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.

  9. A Framework for an Integrated Risk Informed Decision Making Process. INSAG-25. A Report by the International Nuclear Safety Group

    International Nuclear Information System (INIS)

    2011-01-01

    There is general international agreement, as reflected in various IAEA Safety Standards on nuclear reactor design and operation, that both deterministic and probabilistic analyses contribute to reactor safety by providing insights, perspective, comprehension and balance. Accordingly, the integration of deterministic and probabilistic analyses is increasing to support design, safety evaluation and operations. Additionally, application of these approaches to physical security is now being considered by several Member States. Deterministic and probabilistic analyses yield outputs that are complementary to each other. There is thus a need to use a structured framework for consideration of deterministic and probabilistic techniques and findings. In this process, it is appropriate to encourage a balance between deterministic approaches, probabilistic analyses and other factors (see Section 3) in order to achieve an integrated decision making process that serves in an optimal fashion to ensure nuclear reactor safety. This report presents such a framework - a framework that is termed 'integrated risk informed decision making' (IRIDM). While the details of IRIDM methods may change with better understanding of the subject, the framework presented in this report is expected to apply for the foreseeable future. IRIDM depends on the integration of a wide variety of information, insights and perspectives, as well as the commitment of designers, operators and regulatory authorities to use risk information in their decisions. This report thus focuses on key IRIDM aspects, as well considerations that bear on their application which should be taken into account in order to arrive at sound risk informed decisions. This report is intended to be in harmony with the IAEA Safety Standards and various INSAG reports relating to safety assessment and verification, and seeks to convey an appropriate approach to enhance nuclear reactor safety

  10. A Framework for an Integrated Risk Informed Decision Making Process. INSAG-25. A Report by the International Nuclear Safety Group

    International Nuclear Information System (INIS)

    2014-01-01

    There is general international agreement, as reflected in various IAEA Safety Standards on nuclear reactor design and operation, that both deterministic and probabilistic analyses contribute to reactor safety by providing insights, perspective, comprehension and balance. Accordingly, the integration of deterministic and probabilistic analyses is increasing to support design, safety evaluation and operations. Additionally, application of these approaches to physical security is now being considered by several Member States. Deterministic and probabilistic analyses yield outputs that are complementary to each other. There is thus a need to use a structured framework for consideration of deterministic and probabilistic techniques and findings. In this process, it is appropriate to encourage a balance between deterministic approaches, probabilistic analyses and other factors (see Section 3) in order to achieve an integrated decision making process that serves in an optimal fashion to ensure nuclear reactor safety. This report presents such a framework - a framework that is termed 'integrated risk informed decision making' (IRIDM). While the details of IRIDM methods may change with better understanding of the subject, the framework presented in this report is expected to apply for the foreseeable future. IRIDM depends on the integration of a wide variety of information, insights and perspectives, as well as the commitment of designers, operators and regulatory authorities ers, operators and regulatory authorities to use risk information in their decisions. This report thus focuses on key IRIDM aspects, as well considerations that bear on their application which should be taken into account in order to arrive at sound risk informed decisions. This report is intended to be in harmony with the IAEA Safety Standards and various INSAG reports relating to safety assessment and verification, and seeks to convey an appropriate approach to enhance nuclear reactor safety

  11. Integrated approach for combining sustainability and safety into a RAM analysis, RAM2S (Reliability, Availability, Maintainability, Sustainability and Safety) towards greenhouse gases emission targets

    Energy Technology Data Exchange (ETDEWEB)

    Alvarenga, Tobias V. [Det Norske Veritas (DNV), Hovik, Oslo (Norway)

    2009-07-01

    This paper aims to present an approach to integrate sustainability and safety concerns on top of a typical RAM Analysis to support new enterprises to find alternatives to align themselves to the greenhouse gases emission targets, measured as CO{sub 2} (carbon dioxide) equivalent. This approach can be used to measure the impact of the potential CO{sub 2} equivalent emission levels mainly related to new enterprises with high CO{sub 2} content towards environment and production, as per example, the extraction of oil and gas from the Brazilian Pre-salt layers. In this sense, this integrated approach, combining Sustainability and Safety into a RAM analysis, RAM2S (Reliability, Availability, Maintainability, Sustainability and Safety), can be used to assess the impact of CO{sub 2} 'production' along the entire enterprise life-cycle, including the impact of possible facility shutdown due to emission restrictions limits, as well as due to the occurrence of additional failures modes related to CO{sub 2} corrosion capabilities. Thus, at the end, this integrated approach would allow companies to find out a more cost-effective alternative to adapt their business into the global warming reality, overcoming the inherent threats of greenhouse gases. (author)

  12. Integrating environmental management into food safety and food packaging in Malaysia: review of the food regulation 1985

    Science.gov (United States)

    Nordin, N. H.; Hara, H.; Kaida, N.

    2017-05-01

    Food safety is an important issue that is related to public safety to prevent the toxicity threats of the food. Management through legal approach has been used in Malaysia as one of the predominant approaches to manage the environment. In this regard, the Food Regulation 1985 has been one of the mechanisms of environmental management through legal approach in controlling the safety of packaged food in food packaging industry in Malaysia. The present study aims to analyse and to explain the implementation of the Food Regulation 1985 in controlling the safety of packaged food in Malaysia and to integrate the concept of environmental management into the food safety issue. Qualitative analysis on the regulation document revealed that there are two main themes, general and specific, while their seven sub themes are included harmful packages, safety packages, reuse packages, polyvinyl chloride (PVC), alcoholic bottle, toys, money and others and iron powder. The implementation of the Food Regulation 1985 in controlling the safety of packaged food should not be regarded solely for regulation purposes but should be further developed for a broader sense of food safety from overcoming the food poisoning.

  13. Integrating natural language processing expertise with patient safety event review committees to improve the analysis of medication events.

    Science.gov (United States)

    Fong, Allan; Harriott, Nicole; Walters, Donna M; Foley, Hanan; Morrissey, Richard; Ratwani, Raj R

    2017-08-01

    Many healthcare providers have implemented patient safety event reporting systems to better understand and improve patient safety. Reviewing and analyzing these reports is often time consuming and resource intensive because of both the quantity of reports and length of free-text descriptions in the reports. Natural language processing (NLP) experts collaborated with clinical experts on a patient safety committee to assist in the identification and analysis of medication related patient safety events. Different NLP algorithmic approaches were developed to identify four types of medication related patient safety events and the models were compared. Well performing NLP models were generated to categorize medication related events into pharmacy delivery delays, dispensing errors, Pyxis discrepancies, and prescriber errors with receiver operating characteristic areas under the curve of 0.96, 0.87, 0.96, and 0.81 respectively. We also found that modeling the brief without the resolution text generally improved model performance. These models were integrated into a dashboard visualization to support the patient safety committee review process. We demonstrate the capabilities of various NLP models and the use of two text inclusion strategies at categorizing medication related patient safety events. The NLP models and visualization could be used to improve the efficiency of patient safety event data review and analysis. Copyright © 2017 Elsevier B.V. All rights reserved.

  14. Electric Vehicle Based Battery Storages for Large Scale Wind Power Integration in Denmark

    DEFF Research Database (Denmark)

    Pillai, Jayakrishnan Radhakrishna

    In the recent years, the electric vehicles (EVs) have drawn great attention world wide as a feasible solution for clean transportation. The electric vehicle technology is not new as it was introduced in the mid 19th century. The low battery capacity, driving range and superior gasoline cars had...... resulted in the demise of electric cars in the 1930s. However, with the advancement of new high density battery technologies and power electronic converters, it is now viable to produce electric cars of higher efficiency and driving range. The performance and durability of the battery technology...... is improving on a rapid scale and the battery cost is also reducing which could enable the electric cars to be competitive in the market. The electric vehicles could also benefit the electricity sector in supporting more renewable energy which is also one of the most important driving forces in its promotion...

  15. 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.)

  16. A strategic approach to quality improvement and patient safety education and resident integration in a general surgery residency.

    Science.gov (United States)

    O'Heron, Colette T; Jarman, Benjamin T

    2014-01-01

    To outline a structured approach for general surgery resident integration into institutional quality improvement and patient safety education and development. A strategic plan to address Accreditation Council for Graduate Medical Education (ACGME) Clinical Learning Environment Review assessments for resident integration into Quality Improvement and Patient Safety initiatives is described. Gundersen Lutheran Medical Foundation is an independent academic medical center graduating three categorical residents per year within an integrated multi-specialty health system serving 19 counties over 3 states. The quality improvement and patient safety education program includes a formal lecture series, online didactic sessions, mandatory quality improvement or patient safety projects, institutional committee membership, an opportunity to serve as a designated American College of Surgeons National Surgical Quality Improvement Project and Quality in Training representative, mandatory morbidity and mortality conference attendance and clinical electives in rural surgery and international settings. Structured education regarding and participation in quality improvement and patient safety programs are able to be accomplished during general surgery residency. The long-term outcomes and benefits of these strategies are unknown at this time and will be difficult to measure with objective data. © 2013 Published by Association of Program Directors in Surgery on behalf of Association of Program Directors in Surgery.

  17. Implementing a "quality by design" approach to assure the safety and integrity of botanical dietary supplements.

    Science.gov (United States)

    Khan, Ikhlas A; Smillie, Troy

    2012-09-28

    Natural products have provided a basis for health care and medicine to humankind since the beginning of civilization. According to the World Health Organization (WHO), approximately 80% of the world population still relies on herbal medicines for health-related benefits. In the United States, over 42% of the population claimed to have used botanical dietary supplements to either augment their current diet or to "treat" or "prevent" a particular health-related issue. This has led to the development of a burgeoning industry in the U.S. ($4.8 billion per year in 2008) to supply dietary supplements to the consumer. However, many commercial botanical products are poorly defined scientifically, and the consumer must take it on faith that the supplement they are ingesting is an accurate representation of what is listed on the label, and that it contains the purportedly "active" constituents they seek. Many dietary supplement manufacturers, academic research groups, and governmental organizations are progressively attempting to construct a better scientific understanding of natural products, herbals, and botanical dietary supplements that have co-evolved with Western-style pharmaceutical medicines. However, a deficiency of knowledge is still evident, and this issue needs to be addressed in order to achieve a significant level of safety, efficacy, and quality for commercial natural products. The authors contend that a "quality by design" approach for botanical dietary supplements should be implemented in order to ensure the safety and integrity of these products. Initiating this approach with the authentication of the starting plant material is an essential first step, and in this review several techniques that can aid in this endeavor are outlined.

  18. Application of the integrated analysis of safety (ISA) to sequences of Total loss of feed water in a PWR Reactor

    International Nuclear Information System (INIS)

    Moreno Chamorro, P.; Gallego Diaz, C.

    2011-01-01

    The main objective of this work is to show the current status of the implementation of integrated analysis of safety (ISA) methodology and its SCAIS associated tool (system of simulation codes for ISA) to the sequence analysis of total loss of feedwater in a PWR reactor model Westinghouse of three loops with large, dry containment.

  19. 49 CFR 244.13 - Subjects to be addressed in a Safety Integration Plan involving an amalgamation of operations.

    Science.gov (United States)

    2010-10-01

    ... transaction: (a) Corporate culture. Each applicant shall: (1) Identify and describe differences for each safety-related area between the corporate cultures of the railroads involved in the transaction; (2... step-by-step measures, the integration of these corporate cultures and the manner in which it will...

  20. Integrating Safety, Operations, Security, and Safeguards (ISOSS) into the design of small modular reactors : a handbook.

    Energy Technology Data Exchange (ETDEWEB)

    Middleton, Bobby D. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Mendez, Carmen Margarita [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2013-10-01

    The existing regulatory environment for nuclear reactors impacts both the facility design and the cost of operations once the facility is built. Delaying the consideration of regulatory requirements until late in the facility design - or worse, until after construction has begun - can result in costly retrofitting as well as increased operational costs to fulfill safety, security, safeguards, and emergency readiness requirements. Considering the scale and scope, as well as the latest design trends in the next generation of nuclear facilities, there is an opportunity to evaluate the regulatory requirements and optimize the design process for Small Modular Reactors (SMRs), as compared to current Light Water Reactors (LWRs). To this end, Sandia has embarked on an initiative to evaluate the interactions of regulations and operations as an approach to optimizing the design of SMR facilities, supporting operational efficiencies, as well as regulatory requirements. The early stages of this initiative consider two focus areas. The first focus area, reported by LaChance, et al. (2007), identifies the regulatory requirements established for the current fleet of LWR facilities regarding Safety, Security, Operations, Safeguards, and Emergency Planning, and evaluates the technical bases for these requirements. The second focus area, developed in this report, documents the foundations for an innovative approach that supports a design framework for SMR facilities that incorporates the regulatory environment, as well as the continued operation of the facility, into the early design stages, eliminating the need for costly retrofitting and additional operating personnel to fulfill regulatory requirements. The work considers a technique known as Integrated Safety, Operations, Security and Safeguards (ISOSS) (Darby, et al., 2007). In coordination with the best practices of industrial operations, the goal of this effort is to develop a design framework that outlines how ISOSS

  1. The Integrated Safety Management System Verification Enhancement Review of the Plutonium Finishing Plant (PFP)

    International Nuclear Information System (INIS)

    BRIGGS, C.R.

    2000-01-01

    The primary purpose of the verification enhancement review was for the DOE Richland Operations Office (RL) to verify contractor readiness for the independent DOE Integrated Safety Management System Verification (ISMSV) on the Plutonium Finishing Plant (PFP). Secondary objectives included: (1) to reinforce the engagement of management and to gauge management commitment and accountability; (2) to evaluate the ''value added'' benefit of direct public involvement; (3) to evaluate the ''value added'' benefit of direct worker involvement; (4) to evaluate the ''value added'' benefit of the panel-to-panel review approach; and, (5) to evaluate the utility of the review's methodology/adaptability to periodic assessments of ISM status. The review was conducted on December 6-8, 1999, and involved the conduct of two-hour interviews with five separate panels of individuals with various management and operations responsibilities related to PFP. A semi-structured interview process was employed by a team of five ''reviewers'' who directed open-ended questions to the panels which focused on: (1) evidence of management commitment, accountability, and involvement; and, (2) consideration and demonstration of stakeholder (including worker) information and involvement opportunities. The purpose of a panel-to-panel dialogue approach was to better spotlight: (1) areas of mutual reinforcement and alignment that could serve as good examples of the management commitment and accountability aspects of ISMS implementation, and, (2) areas of potential discrepancy that could provide opportunities for improvement. In summary, the Review Team found major strengths to include: (1) the use of multi-disciplinary project work teams to plan and do work; (2) the availability and broad usage of multiple tools to help with planning and integrating work; (3) senior management presence and accessibility; (4) the institutionalization of worker involvement; (5) encouragement of self-reporting and self

  2. Probabilistic safety assessment of Tehran Research Reactor using systems analysis programs for hands-on integrated reliability evaluations

    International Nuclear Information System (INIS)

    Hosseini, M.H.; Nematollahi, M.R.; Sepanloo, K.

    2004-01-01

    Probabilistic safety assessment application is found to be a practical tool for research reactor safety due to intense involvement of human interactions in an experimental facility. In this document the application of the probabilistic safety assessment to the Tehran Research Reactor is presented. The level 1 practicabilities safety assessment application involved: Familiarization with the plant, selection of accident initiators, mitigating functions and system definitions, event tree constructions and quantifications, fault tree constructions and quantification, human reliability, component failure data base development and dependent failure analysis. Each of the steps of the analysis given above is discussed with highlights from the selected results. Quantification of the constructed models is done using systems analysis programs for hands-on integrated reliability evaluations software

  3. Safety Lead Optimization and Candidate Identification: Integrating New Technologies into Decision-Making.

    Science.gov (United States)

    Dambach, Donna M; Misner, Dinah; Brock, Mathew; Fullerton, Aaron; Proctor, William; Maher, Jonathan; Lee, Dong; Ford, Kevin; Diaz, Dolores

    2016-04-18

    Discovery toxicology focuses on the identification of the most promising drug candidates through the development and implementation of lead optimization strategies and hypothesis-driven investigation of issues that enable rational and informed decision-making. The major goals are to [a] identify and progress the drug candidate with the best overall drug safety profile for a therapeutic area, [b] remove the most toxic drugs from the portfolio prior to entry into humans to reduce clinical attrition due to toxicity, and [c] establish a well-characterized hazard and translational risk profile to enable clinical trial designs. This is accomplished through a framework that balances the multiple considerations to identify a drug candidate with the overall best drug characteristics and provides a cogent understanding of mechanisms of toxicity. The framework components include establishing a target candidate profile for each program that defines the qualities of a successful candidate based on the intended therapeutic area, including the risk tolerance for liabilities; evaluating potential liabilities that may result from engaging the therapeutic target (pharmacology-mediated or on-target) and that are chemical structure-mediated (off-target); and characterizing identified liabilities. Lead optimization and investigation relies upon the integrated use of a variety of technologies and models (in silico, in vitro, and in vivo) that have achieved a sufficient level of qualification or validation to provide confidence in their use. We describe the strategic applications of various nonclinical models (established and new) for a holistic and integrated risk assessment that is used for rational decision-making. While this review focuses on strategies for small molecules, the overall concepts, approaches, and technologies are generally applicable to biotherapeutics.

  4. Evaluation of Advanced Thermohydraulic System Codes for Design and Safety Analysis of Integral Type Reactors

    International Nuclear Information System (INIS)

    2014-02-01

    The integral pressurized water reactor (PWR) concept, which incorporates the nuclear steam supply systems within the reactor vessel, is one of the innovative reactor types with high potential for near term deployment. An International Collaborative Standard Problem (ICSP) on Integral PWR Design, Natural Circulation Flow Stability and Thermohydraulic Coupling of Primary System and Containment during Accidents was established in 2010. Oregon State University, which made available the use of its experimental facility built to demonstrate the feasibility of the Multi-application Small Light Water Reactor (MASLWR) design, and sixteen institutes from seven Member States participated in this ICSP. The objective of the ICSP is to assess computer codes for reactor system design and safety analysis. This objective is achieved through the production of experimental data and computer code simulation of experiments. A loss of feedwater transient with subsequent automatic depressurization system blowdown and long term cooling was selected as the reference event since many different modes of natural circulation phenomena, including the coupling of primary system, high pressure containment and cooling pool are expected to occur during this transient. The power maneuvering transient is also tested to examine the stability of natural circulation during the single and two phase conditions. The ICSP was conducted in three phases: pre-test (with designed initial and boundary conditions established before the experiment was conducted), blind (with real initial and boundary conditions after the experiment was conducted) and open simulation (after the observation of real experimental data). Most advanced thermohydraulic system analysis codes such as TRACE, RELAPS and MARS have been assessed against experiments conducted at the MASLWR test facility. The ICSP has provided all participants with the opportunity to evaluate the strengths and weaknesses of their system codes in the transient

  5. Integrated Chassis Control System with Fail Safety Using Optimum Yaw Moment Distribution

    International Nuclear Information System (INIS)

    Yim, Seongjin

    2014-01-01

    This paper presents an integrated chassis control system with fail safety using optimum yaw moment distribution for a vehicle with steer-by-wire and brake-by-wire devices. The proposed system has two-level structure: upper- and lower-level controllers. In the upper-level controller, the control yaw moment is computed with sliding mode control theory. In the lower-level controller, the control yaw moment is distributed into the tire forces of active front steering(AFS) and electronic stability control(ESC) with the weighted pseudo-inverse based control allocation(WPCA) method. By setting the variable weights in WPCA, it is possible to take the sensor/actuator failure into account. In this framework, it is necessary to optimize the variables weights in order to enhance the yaw moment distribution. For this purpose, simulation-based tuning is proposed. To show the effectiveness of the proposed method, simulations are conducted on a vehicle simulation package, CarSim

  6. Integrated Chassis Control System with Fail Safety Using Optimum Yaw Moment Distribution

    Energy Technology Data Exchange (ETDEWEB)

    Yim, Seongjin [Seoul Nat' l Univ. of Sci. and Tech., Seoul (Korea, Republic of)

    2014-03-15

    This paper presents an integrated chassis control system with fail safety using optimum yaw moment distribution for a vehicle with steer-by-wire and brake-by-wire devices. The proposed system has two-level structure: upper- and lower-level controllers. In the upper-level controller, the control yaw moment is computed with sliding mode control theory. In the lower-level controller, the control yaw moment is distributed into the tire forces of active front steering(AFS) and electronic stability control(ESC) with the weighted pseudo-inverse based control allocation(WPCA) method. By setting the variable weights in WPCA, it is possible to take the sensor/actuator failure into account. In this framework, it is necessary to optimize the variables weights in order to enhance the yaw moment distribution. For this purpose, simulation-based tuning is proposed. To show the effectiveness of the proposed method, simulations are conducted on a vehicle simulation package, CarSim.

  7. Integrating building information modeling and health and safety for onsite construction.

    Science.gov (United States)

    Ganah, Abdulkadir; John, Godfaurd A

    2015-03-01

    Health and safety (H&S) on a construction site can either make or break a contractor, if not properly managed. The usage of Building Information Modeling (BIM) for H&S on construction execution has the potential to augment practitioner understanding of their sites, and by so doing reduce the probability of accidents. This research explores BIM usage within the construction industry in relation to H&S communication. In addition to an extensive literature review, a questionnaire survey was conducted to gather information on the embedment of H&S planning with the BIM environment for site practitioners. The analysis of responses indicated that BIM will enhance the current approach of H&S planning for construction site personnel. From the survey, toolbox talk will have to be integrated with the BIM environment, because it is the predominantly used procedure for enhancing H&S issues within construction sites. The advantage is that personnel can visually understand H&S issues as work progresses during the toolbox talk onsite.

  8. SAFETY

    CERN Multimedia

    M. Plagge, C. Schaefer and N. Dupont

    2013-01-01

    Fire Safety – Essential for a particle detector The CMS detector is a marvel of high technology, one of the most precise particle measurement devices we have built until now. Of course it has to be protected from external and internal incidents like the ones that can occur from fires. Due to the fire load, the permanent availability of oxygen and the presence of various ignition sources mostly based on electricity this has to be addressed. Starting from the beam pipe towards the magnet coil, the detector is protected by flooding it with pure gaseous nitrogen during operation. The outer shell of CMS, namely the yoke and the muon chambers are then covered by an emergency inertion system also based on nitrogen. To ensure maximum fire safety, all materials used comply with the CERN regulations IS 23 and IS 41 with only a few exceptions. Every piece of the 30-tonne polyethylene shielding is high-density material, borated, boxed within steel and coated with intumescent (a paint that creates a thick co...

  9. SAFETY

    CERN Multimedia

    C. Schaefer and N. Dupont

    2013-01-01

      “Safety is the highest priority”: this statement from CERN is endorsed by the CMS management. An interpretation of this statement may bring you to the conclusion that you should stop working in order to avoid risks. If the safety is the priority, work is not! This would be a misunderstanding and misinterpretation. One should understand that “working safely” or “operating safely” is the priority at CERN. CERN personnel are exposed to different hazards on many levels on a daily basis. However, risk analyses and assessments are done in order to limit the number and the gravity of accidents. For example, this process takes place each time you cross the road. The hazard is the moving vehicle, the stake is you and the risk might be the risk of collision between both. The same principle has to be applied during our daily work. In particular, keeping in mind the general principles of prevention defined in the late 1980s. These principles wer...

  10. NuSEE: an integrated environment of software specification and V and V for PLC based safety-critical systems

    International Nuclear Information System (INIS)

    Koo, Seo Ryong; Seong, Poong Hyun; Yoo, Jun Beom; Cha, Sung Deok; Youn, Cheong; Han, Hyun Chul

    2006-01-01

    As the use of digital systems becomes more prevalent, adequate techniques for software specification and analysis have become increasingly important in Nuclear Power Plant (NPP) safety-critical systems. Additionally, the importance of software Verification and Validation (V and V) based on adequate specification has received greater emphasis in view of improving software quality. For thorough V and V of safety-critical systems, V and V should be performed throughout the software lifecycle. However, systematic V and V is difficult as it involves many manual-oriented tasks. Tool support is needed in order to more conveniently perform software V and V. In response, we developed four kinds of Computer Aided Software Engineering (CASE) tools to support system specification for a formal-based analysis according to the software lifecycle. In this work, we achieved optimized integration of each tool. The toolset, NuSEE, is an integrated environment for software specification and V and V for PLC based safety-critical systems. In accordance with the software lifecycle, NuSEE consists of NuSISRT for the concept phase, NuSRS for the requirements phase, NuSDS for the design phase and NuSCM for configuration management. It is believed that after further development our integrated environment will be a unique and promising software specification and analysis toolset that will support the entire software lifecycle for the development of PLC based NPP safety-critical systems

  11. OCCUPATIONAL HEALTH AND SAFETY INTEGRATION IN CORPORATE SOCIAL RESPONSIBILITY POLICIES WITHIN B.R.D. - G.S.G. ROMANIA

    Directory of Open Access Journals (Sweden)

    CODRUŢA DURA

    2014-10-01

    Full Text Available Corporate Social Responsibility can be an opportunity for integration and approach of issues related to Occupational Health and Safety, seen from a broader perspective than that of mere correlation with legislation. The present paper aims at analysing the way the growing interest, in terms of Corporate Social Responsibility, can contribute to improving the implementation of appropriate systems to prevent accidents at work within Romanian organisations. The case study that illustrates the good practices of BRD-Groupe Société Générale revealed the role of the instruments analysed as catalysts for improving the activity of occupational safety and health.

  12. Safety

    International Nuclear Information System (INIS)

    Jones, P.M.S.

    1987-01-01

    Aspects of fission reactors are considered - control, heat removal and containment. Brief descriptions of the reactor accidents at the SL-1 reactor (1961), Windscale (1957), Browns Ferry (1975), Three Mile Island (1979) and Chernobyl (1986) are given. The idea of inherently safe reactor designs is discussed. Safety assessment is considered under the headings of preliminary hazard analysis, failure mode analysis, event trees, fault trees, common mode failure and probabalistic risk assessments. These latter can result in a series of risk distributions linked to specific groups of fault sequences and specific consequences. A frequency-consequence diagram is shown. Fatal accident incidence rates in different countries including the United Kingdom for various industries are quoted. The incidence of fatal cancers from occupational exposure to chemicals is tabulated. Human factors and the acceptability of risk are considered. (U.K.)

  13. Passive Strategy with Integrated Passive Safety System (IPSS) for DBAs in SBO

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sang Ho; Kim, Jihee; Choi, Jae Young; Jeon, Inseop; Chang, Soon Heung [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

    2013-10-15

    Beznau nuclear power plant. The third solution is to make a cooling redundancy. Integrated passive safety system (IPSS) proposed in 2011 is a representative design adding big water tanks outside containment on a top of auxiliary building as a heat sink and water supplier. Three methods are each merit and demerit. After the design concept of IPSS was proposed, main functions were analyzed to be verified. With the simulated performances of IPSS in conservative conditions, passive counter strategies to cope with design based accidents (DBAs) were proposed and described in a basic condition of a SBO.

  14. APMS: An Integrated Suite of Tools for Measuring Performance and Safety

    Science.gov (United States)

    Statler, Irving C.; Lynch, Robert E.; Connors, Mary M. (Technical Monitor)

    1997-01-01

    statistical evaluation of the performance of large groups of flights. This paper describes the integrated suite of tools that will assist analysts in evaluating the operational performance and safety of the national air transport system, the air carrier, and the air crew.

  15. The Aviation Performance Measuring System (APMS): An Integrated Suite of Tools for Measuring Performance and Safety

    Science.gov (United States)

    Statler, Irving C.; Connor, Mary M. (Technical Monitor)

    1998-01-01

    statistical evaluation of the performance of large groups of flights. This paper describes the integrated suite of tools that will assist analysts in evaluating the operational performance and safety of the national air transport system, the air carrier, and the aircrew.

  16. IAEA'S International Working Group on Integrated Transport and Storage Safety case for Dual Purpose Casks

    International Nuclear Information System (INIS)

    Kumano, Yumiko; Varley, Kasturi; ); Droste, Bernhard; Wolff, Dietmar; Hirose, Makoto; Harvey, John; Reiche, Ingo; McConnell, Paul

    2014-01-01

    Spent nuclear fuel is generated from the operation of nuclear reactors and it is imperative that it is safely managed following its removal from reactor cores. Reactor pools are usually designed based on the assumption that the fuel will be removed after a short period of time either for reprocessing, disposal, or further storage. As a result of storing higher burn-up fuel, significantly increased time-frame till disposal solutions are prepared, and delays in decisions on strategies for spent fuel management, the volume of spent fuel discharged from reactors which needs to be managed and stored is on the increase. Consequently, additional storage capacity is needed following the initial storage in reactor pools. Options for additional storage include wet storage or dry storage in a dedicated facility or in storage casks. One of these options is the use of a Dual Purpose Cask (DPC), which is a specially designed cask for both storage and transport. The management of spent fuel using a DPC generally involves on-site and off-site transportation before and after storage. Most countries require package design approval for the DPC to be transported. In addition, it is required in many countries to have a licence for storage of the spent fuel in the DPC or a licence for a storage facility that contains DPCs. Therefore, demonstration of compliance of the DPC with national and international transport regulations as well as with the storage requirements is necessary. In order to address this increasing need among Member States, the IAEA established an international working group in 2010 to develop a guidance for integrating safety cases for both storage and transport in a holistic manner. The working group consists of experts from regulatory bodies, Technical Support Organizations, operators for both transportation and storage, and research institutes. This activity is planned to be completed by 2013. Currently, a technical report has been drafted and is expected to be

  17. PSA Level 2 as element of an integral safety assessment before plant commissioning

    International Nuclear Information System (INIS)

    Loeffler, H.; Mildenberger, O.; Sonnenkalb, M.; Steinroetter, T.

    2012-01-01

    In Argentina the Central Nuclear Atucha II is near to completion. This is a pressurized heavy water reactor. PSA (Probability Safety Assessment) level 1, level 2 and level 3 have to be performed in order to show compliance with the Argentinean dose limit. Such studies have been done first by the former KWU in the 1980's to get the construction license (FABIAN 1985). Nowadays the plant owner NA-SA performs PSA level 1 and provides information about the core damage states to GRS, who does the subsequent PSA level 2 part. GRS delivers source terms to the environment and the associated frequencies to the Argentinean research institute CNEA, which performs level 3 together with NA-SA. Since GRS is situated in the middle of the chain, interface definition with both ends has been a significant task of the GRS activities. Experience gained during this process will be highlighted in the presentation. The analysis of PSA level 2 proper follows a traditional approach: -) deterministic accident simulation with integral code MELCOR; -) analyses of specific issues which are not covered by MELCOR; and -) probabilistic accident progression analysis with EVNTRE event tree methodology. It appears that MELCOR and EVNTRE and PSA guidelines in general are flexible enough to analyse new or uncommon reactor designs. It also appears that the plant specific design features may require analyses beyond present code capabilities, calling for expert judgment and they can largely determine PSA results. The behaviour of iodine is not yet covered satisfactorily by state-of-the-art models in MELCOR

  18. Integrating psychosocial safety climate in the JD-R model: A study amongst Malaysian workers

    Directory of Open Access Journals (Sweden)

    Mohd A. Idris

    2011-05-01

    Research purpose: We expanded the Job Demands and Resources (JD-R model by proposing psychosocial safety climate (PSC as a precursor to job demands and job resources. As PSC theoretically influences the working environment, the study hypothesized that PSC has an impact on performance via both health erosion (i.e. burnout and motivational pathways (i.e. work engagement. Motivation for the study: So far, integration of PSC in the JD-R model is only tested in a Western context (i.e. Australia. We tested the emerging construct of PSC in Malaysia, an Eastern developing country in the Asian region. Research design, approach and method: A random population based sample was derived using household maps provided by Department of Statistics, Malaysia; 291 employees (response rate 50.52% from the State of Selangor, Malaysia participated. Cross-sectional data were analysed using structural equation modelling. Main findings: We found that PSC was negatively related to job demands and positively related to job resources. Job demands, in turn, predicted burnout (i.e. exhaustion and cynicism, whereas job resources predicted engagement. Both burnout and engagement were associated with performance. Bootstrapping showed significant indirect effects of PSC on burnout via job demands, PSC on performance via burnout and PSC on performance via the resources-engagement pathway. Practical/managerial implications: Our findings are consistent with previous research that suggests that PSC should be a target to improve working conditions and in turn reduce burnout and improve engagement and productivity. Contribution/value-add: These findings suggest that JD-R theory may be expanded to include PSC as an antecedent and that the expanded JD-R model is largely valid in an Eastern, developing economy setting.

  19. Integrated plant safety assessment: systematic evaluation program. Haddam Neck Plant, Connecticut Yankee Atomic Power Company. Docket No. 50-213

    International Nuclear Information System (INIS)

    1983-03-01

    The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of Haddam Neck Plant, operated by Connecticut Yankee Atomic Power Company. The Haddam Neck Plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review

  20. Development of integrated D/B system for the safety-related structures in nuclear power plant

    International Nuclear Information System (INIS)

    Cho, M. S.; Song, Y. C.; Lee, J. S.; Choi, W. S.

    2002-01-01

    The integrated D/B system is developed for digitalizing the history of the safety-related structures of nuclear power plant. It have 5 database which are consist of Generals, Structural and Design, Materials, Construction, Aging and repair information D/B. For efficient operation of the system, we are to set up the outline of the system, find out data field for target structures, and develop utilities. Utilities will be the aging and repair data management program, the close examination management program, the data search engine with various options which help users to find the information quickly, and the data management program restoring, updating and exchanging input data. Development of the integrated D/B system of the safety-related structures will contribute to management of the structures of nuclear power plant with advanced technology

  1. Technical findings and regulatory analysis for Generic Safety Issue II.E.4.3, ''Containment Integrity Check''

    International Nuclear Information System (INIS)

    Serkiz, A.W.

    1988-04-01

    This report contains the technical findings and regulatory analysis for Generic Safety Issue II.E.4.3, ''Containment Integrity Check.'' An evaluation of the containment isolation history from 1965 to 1983 reveals that (except for a small number of events) containment integrity has been maintained and that the majority of reported events have been events related to exceeding Technical Specification limits (or 0.6 of the allowable leakage level). In addition, more recent risk analyses have shown that allowable leakage rates even if increased by a factor of 10 would not significantly increase risk. Potential methods of continuous monitoring are identified and evaluated. Therefore, these technical findings and risk evaluations support closure of Generic Safety Issue II.E.4.3

  2. Integrating teamwork, clinician occupational well-being and patient safety - development of a conceptual framework based on a systematic review.

    Science.gov (United States)

    Welp, Annalena; Manser, Tanja

    2016-07-19

    There is growing evidence that teamwork in hospitals is related to both patient outcomes and clinician occupational well-being. Furthermore, clinician well-being is associated with patient safety. Despite considerable research activity, few studies include all three concepts, and their interrelations have not yet been investigated systematically. To advance our understanding of these potentially complex interrelations we propose an integrative framework taking into account current evidence and research gaps identified in a systematic review. We conducted a literature search in six major databases (Medline, PsycArticles, PsycInfo, Psyndex, ScienceDirect, and Web of Knowledge). Inclusion criteria were: peer reviewed papers published between January 2000 and June 2015 investigating a statistical relationship between at least two of the three concepts; teamwork, patient safety, and clinician occupational well-being in hospital settings, including practicing nurses and physicians. We assessed methodological quality using a standardized rating system and qualitatively appraised and extracted relevant data, such as instruments, analyses and outcomes. The 98 studies included in this review were highly diverse regarding quality, methodology and outcomes. We found support for the existence of independent associations between teamwork, clinician occupational well-being and patient safety. However, we identified several conceptual and methodological limitations. The main barrier to advancing our understanding of the causal relationships between teamwork, clinician well-being and patient safety is the lack of an integrative, theory-based, and methodologically thorough approach investigating the three concepts simultaneously and longitudinally. Based on psychological theory and our findings, we developed an integrative framework that addresses these limitations and proposes mechanisms by which these concepts might be linked. Knowledge about the mechanisms underlying the

  3. *Abstracts - 7th IN-CAM Research Symposium, Evaluating CAM Practices: Effectiveness, Integration, Economics & Safety - November 2012.

    Science.gov (United States)

    Boon, Heather; Verhoef, Marja J

    2012-10-23

    Abstract The following are abstracts of oral and poster presentations given at the 7th IN-CAM Research Symposium - Evaluating CAM Practices: Effectiveness, Integration, Economics & Safety, and the 4th HomeoNet Research Forum, a pre-Symposium event. The IN-CAM Research Symposium was held November 2 to 4, 2012 at the Leslie Dan Faculty of Pharmacy, University of Toronto, in Toronto, Ontario, Canada. For more information, please visit: www.incamresearch.ca.

  4. Integrated plant safety assessment. Systematic evaluation program, Big Rock Point Plant (Docket No. 50-155). Final report

    International Nuclear Information System (INIS)

    1984-05-01

    The Systematic Evaluation Program was initiated in February 1977 by the U.S. Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to reconfirm and document their safety. The review provides (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety when the supplement to the Final Integrated Plant Safety Assessment Report has been issued. This report documents the review of the Big Rock Point Plant, which is one of ten plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. It also addresses a majority of the pending licensing actions for Big Rock Point, which include TMI Action Plan requirements and implementation criteria for resolved generic issues. Equipment and procedural changes have been identified as a result of the review

  5. Integration of the advanced transparency framework to advanced nuclear systems : enhancing Safety, Operations, Security and Safeguards (SOSS)

    International Nuclear Information System (INIS)

    Mendez, Carmen Margarita; Rochau, Gary Eugene; Cleary, Virginia D.

    2008-01-01

    The advent of the nuclear renaissance gives rise to a concern for the effective design of nuclear fuel cycle systems that are safe, secure, nonproliferating and cost-effective. We propose to integrate the monitoring of the four major factors of nuclear facilities by focusing on the interactions between Safeguards, Operations, Security, and Safety (SOSS). We proposed to develop a framework that monitors process information continuously and can demonstrate the ability to enhance safety, operations, security, and safeguards by measuring and reducing relevant SOSS risks, thus ensuring the safe and legitimate use of the nuclear fuel cycle facility. A real-time comparison between expected and observed operations provides the foundation for the calculation of SOSS risk. The automation of new nuclear facilities requiring minimal manual operation provides an opportunity to utilize the abundance of process information for monitoring SOSS risk. A framework that monitors process information continuously can lead to greater transparency of nuclear fuel cycle activities and can demonstrate the ability to enhance the safety, operations, security and safeguards associated with the functioning of the nuclear fuel cycle facility. Sandia National Laboratories (SNL) has developed a risk algorithm for safeguards and is in the process of demonstrating the ability to monitor operational signals in real-time though a cooperative research project with the Japan Atomic Energy Agency (JAEA). The risk algorithms for safety, operations and security are under development. The next stage of this work will be to integrate the four algorithms into a single framework

  6. NRC integrated program for the resolution of Unresolved Safety Issues A-3, A-4 and A-5 regarding steam generator tube integrity: Final report

    International Nuclear Information System (INIS)

    1988-09-01

    This report presents the results of the NRC integrated program for the resolution of Unresolved Safety Issues (USIs) A-3, A-4, and A-5 regarding steam generator tube integrity. A generic risk assessment is provided and indicates that risk from steam generator tube rupture (SGTR) events is not a significant contributor to total risk at a given site, nor to the total risk to which the general public is routinely exposed. This finding is considered to be indicative of the effectiveness of licensee programs and regulatory requirements for ensuring steam generator tube integrity in accordance with 10 CFR 50, Appendices A and B. This report also identifies a number of staff-recommended actions that the staff finds can further improve the effectiveness of licensee programs in ensuring the integrity of steam generator tubes and in mitigating the consequences of an SGTR. As part of the integrated program, the staff issued Generic Letter 85-02 encouraging licensees of pressurized water reactors (PWRs) to upgrade their programs, as necessary, to meet the intent of the staff-recommended actions; however, such actions do not constitute NRC requirements. In addition, this report describes a number of ongoing staff actions and studies involving steam generator issues which are being pursued to provide added assurance that risk from SGTR events will continue to be small. 146 refs., 5 figs., 11 tabs

  7. Computational methods assuring nuclear power plant structural integrity and safety: an overview of the recent activities at VTT

    International Nuclear Information System (INIS)

    Keinaenen, H.; Talja, H.; Rintamaa, R.

    1998-01-01

    Numerical, simplified engineering and standardised methods are applied in the safety analyses of primary circuit components and reactor pressure vessels. The integrity assessment procedures require input relating both to the steady state and transient loading actual material properties data and precise knowledge of the size and geometry of defects. Current procedures bold extensive information regarding these aspects. It is important to verify the accuracy of the different assessment methods especially in the case of complex structures and loading. The focus of this paper is on the recent results and development of computational fracture assessment methods at VTT Manufacturing Technology. The methods include effective engineering type tools for rapid structural integrity assessments and more sophisticated finite-element based methods. An integrated PC-based program system MASI for engineering fracture analysis is described. A summary of the verification of the methods in computational benchmark analyses and against the results of large scale experiments is presented. (orig.)

  8. Integrating psychosocial safety climate in the JD-R model: a study amongst Malaysian workers

    OpenAIRE

    Idris, Mohd A.; Dollard, Maureen F.; Winefield, Anthony H.

    2011-01-01

    Orientation: Job characteristics are well accepted as sources of burnout and engagement amongst employees; psychosocial safety climate may precede work conditions. Research purpose: We expanded the Job Demands and Resources (JD-R) model by proposing psychosocial safety climate (PSC) as a precursor to job demands and job resources. As PSC theoretically influences the working environment, the study hypothesized that PSC has an impact on performance via both health erosion (i.e. burnout) and ...

  9. RBMK fuel channel integrity. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1999-01-01

    The fuel channel integrity in the RBMK NPPs is an issue of high safety concern. To date, three single fuel channel ruptures have occurred. Fuel channel rupture results in release of radioactivity to the reactor cavity and may lead to a release of radioactivity to the environment if the confinement safety system does not function properly. A multiple fuel channel rupture exceeding the venting capacity of the reactor cavity overpressure protection system poses a major impact on the plant safety. Further, due to incorrect prediction at the design stage the gas gap between the fuel channel pressure tube and the graphite blocks closes after approximately 17 years of plant operation. There is no safety justification available for the continued plant operation in this condition and the reactors are being retubed to avoid operation in this out of design condition, which may have negative impact on the fuel channel integrity. The loss of the mechanical integrity of fuel channel pressure tubes is a major safety concern for RBMK reactors since it may lead to overpressurization of the reactor cavity and consequently develop into a severe accident. In this report, information on the main design features of the RBMK reactor related to the fuel channel integrity is given. Further, detailed information on the fuel channel pressure tube and the graphite blocks with respect to their design, manufacture, in-service inspection, operating experience, ageing behaviour including degradation mechanisms is discussed in detail. The behaviour of the system fuel channel-graphite core including the corrective actions developed and implemented is discussed. Both normal operating conditions and accident conditions are addressed, considering also the gas gap closure process and its impact. The report also covers the fuel channel ducts. It is concluded in the report that for RBMK-1000 reactors and the adopted retubing strategy, limited local gas gap closure occurs at the time of pressure tube

  10. A Real-Time Construction Safety Monitoring System for Hazardous Gas Integrating Wireless Sensor Network and Building Information Modeling Technologies.

    Science.gov (United States)

    Cheung, Weng-Fong; Lin, Tzu-Hsuan; Lin, Yu-Cheng

    2018-02-02

    In recent years, many studies have focused on the application of advanced technology as a way to improve management of construction safety management. A Wireless Sensor Network (WSN), one of the key technologies in Internet of Things (IoT) development, enables objects and devices to sense and communicate environmental conditions; Building Information Modeling (BIM), a revolutionary technology in construction, integrates database and geometry into a digital model which provides a visualized way in all construction lifecycle management. This paper integrates BIM and WSN into a unique system which enables the construction site to visually monitor the safety status via a spatial, colored interface and remove any hazardous gas automatically. Many wireless sensor nodes were placed on an underground construction site and to collect hazardous gas level and environmental condition (temperature and humidity) data, and in any region where an abnormal status is detected, the BIM model will alert the region and an alarm and ventilator on site will start automatically for warning and removing the hazard. The proposed system can greatly enhance the efficiency in construction safety management and provide an important reference information in rescue tasks. Finally, a case study demonstrates the applicability of the proposed system and the practical benefits, limitations, conclusions, and suggestions are summarized for further applications.

  11. Integrated plant safety assessment, Systematic Evaluation Program: Dresden Nuclear Power Station, Unit 2 (Docket No. 50-237)

    International Nuclear Information System (INIS)

    1989-10-01

    The US Nuclear Regulatory Commission (NRC) has prepared Supplement 1 to the final Integrated Plant Safety Assessment Report (IPSAR) (NUREG-0823), under the scope of the Systematic Evaluation Program (SEP), for the Commonwealth Edison Company (CECo) Dresden Nuclear Power Station, Unit 2 located in Grundy County, Illinois. The NRC initiated the SEP to provide the framework for reviewing the design of older operating nuclear reactor plants to reconfirm and document their safety. This report documents the review completed by means of the SEP for those issues that required refined engineering evaluations or the continuation of ongoing evaluations subsequent to issuing the final IPSAR for Dresden Unit 2. The review was provided for (1) an assessment of the significance of differences between current technical positions on selected issues and those that existed when Dresden Unit 2 was licensed, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. The final IPSAR and this supplement forms part of the bases for considering the conversion of the existing provisional operating license to a full-term operating license. 83 refs., 9 tabs

  12. A passive decay heat removal strategy of the integrated passive safety system (IPSS) for SBO combined with LOCA

    International Nuclear Information System (INIS)

    Kim, Sang Ho; Chang, Soon Heung; Choi, Yu Jung; Jeong, Yong Hoon

    2015-01-01

    Highlights: • A new PDHR strategy is proposed to cope with SBO-combined accidents. • The concept of integrated passive safety system (IPSS) is used in this strategy. • This strategy performs the functions of passive safety injection and SG gravity injection. • LOCAs in SBO are classified by the pressures in reactor coolant system for passive functions. • The strategy can be integrated with EOP and SAMG as a complementary strategy for ensuring safety. - Abstract: An integrated passive safety system (IPSS), to be achieved by the use of a large water tank placed at high elevation outside the containment, was proposed to achieve various passive functions. These include decay heat removal, safety injection, containment cooling, in-vessel retention through external reactor vessel cooling, and containment filtered venting. The purpose of the passive decay heat removal (PDHR) strategy using the IPSS is to cope with SBO and SBO-combined accidents under the assumption that existing engineered safety features have failed. In this paper, a PDHR strategy was developed based on the design and accident management strategy of Korean representative PWR, the OPR1000. The functions of a steam generator gravity injection and a passive safety injection system in the IPSS with safety depressurization systems were included in the PDHR strategy. Because the inadvertent opening of pressurizer valves and seal water leakage from RCPs could cause a loss of coolant in an SBO, LOCAs during a SBO were simulated to verify the performance of the strategy. The failure of active safety injection in LOCAs could also be covered by this strategy. Although LOCAs have generally been categorized according to their equivalent break diameters, the RCS pressure is used to classify the LOCAs during SBOs. The criteria values for categorization were determined from the proposed systems, which could maintain a reactor in a safe state by removing the decay heat for the SBO coping time of 8 h. The

  13. A passive decay heat removal strategy of the integrated passive safety system (IPSS) for SBO combined with LOCA

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sang Ho [Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 291, Daehak-ro, Yuseong-gu, Daejeon 34141 (Korea, Republic of); Chang, Soon Heung [Handong Global University, 558, Handong-ro, Buk-gu, Pohang Gyeongbuk 37554 (Korea, Republic of); Choi, Yu Jung [Korea Hydro and Nuclear Power Co.—Central Research Institute, 70, 1312-gil, Yuseong-daero, Yuseong-gu, Daejeon 34101 (Korea, Republic of); Jeong, Yong Hoon, E-mail: jeongyh@kaist.ac.kr [Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 291, Daehak-ro, Yuseong-gu, Daejeon 34141 (Korea, Republic of)

    2015-12-15

    Highlights: • A new PDHR strategy is proposed to cope with SBO-combined accidents. • The concept of integrated passive safety system (IPSS) is used in this strategy. • This strategy performs the functions of passive safety injection and SG gravity injection. • LOCAs in SBO are classified by the pressures in reactor coolant system for passive functions. • The strategy can be integrated with EOP and SAMG as a complementary strategy for ensuring safety. - Abstract: An integrated passive safety system (IPSS), to be achieved by the use of a large water tank placed at high elevation outside the containment, was proposed to achieve various passive functions. These include decay heat removal, safety injection, containment cooling, in-vessel retention through external reactor vessel cooling, and containment filtered venting. The purpose of the passive decay heat removal (PDHR) strategy using the IPSS is to cope with SBO and SBO-combined accidents under the assumption that existing engineered safety features have failed. In this paper, a PDHR strategy was developed based on the design and accident management strategy of Korean representative PWR, the OPR1000. The functions of a steam generator gravity injection and a passive safety injection system in the IPSS with safety depressurization systems were included in the PDHR strategy. Because the inadvertent opening of pressurizer valves and seal water leakage from RCPs could cause a loss of coolant in an SBO, LOCAs during a SBO were simulated to verify the performance of the strategy. The failure of active safety injection in LOCAs could also be covered by this strategy. Although LOCAs have generally been categorized according to their equivalent break diameters, the RCS pressure is used to classify the LOCAs during SBOs. The criteria values for categorization were determined from the proposed systems, which could maintain a reactor in a safe state by removing the decay heat for the SBO coping time of 8 h. The

  14. Integrate genome-based assessment of safety for probiotic strains: Bacillus coagulans GBI-30, 6086 as a case study.

    Science.gov (United States)

    Salvetti, Elisa; Orrù, Luigi; Capozzi, Vittorio; Martina, Alessia; Lamontanara, Antonella; Keller, David; Cash, Howard; Felis, Giovanna E; Cattivelli, Luigi; Torriani, Sandra; Spano, Giuseppe

    2016-05-01

    Probiotics are microorganisms that confer beneficial effects on the host; nevertheless, before being allowed for human consumption, their safety must be verified with accurate protocols. In the genomic era, such procedures should take into account the genomic-based approaches. This study aims at assessing the safety traits of Bacillus coagulans GBI-30, 6086 integrating the most updated genomics-based procedures and conventional phenotypic assays. Special attention was paid to putative virulence factors (VF), antibiotic resistance (AR) genes and genes encoding enzymes responsible for harmful metabolites (i.e. biogenic amines, BAs). This probiotic strain was phenotypically resistant to streptomycin and kanamycin, although the genome analysis suggested that the AR-related genes were not easily transferrable to other bacteria, and no other genes with potential safety risks, such as those related to VF or BA production, were retrieved. Furthermore, no unstable elements that could potentially lead to genomic rearrangements were detected. Moreover, a workflow is proposed to allow the proper taxonomic identification of a microbial strain and the accurate evaluation of risk-related gene traits, combining whole genome sequencing analysis with updated bioinformatics tools and standard phenotypic assays. The workflow presented can be generalized as a guideline for the safety investigation of novel probiotic strains to help stakeholders (from scientists to manufacturers and consumers) to meet regulatory requirements and avoid misleading information.

  15. Experimental assessment of computer codes used for safety analysis of integral reactors

    Energy Technology Data Exchange (ETDEWEB)

    Falkov, A.A.; Kuul, V.S.; Samoilov, O.B. [OKB Mechanical Engineering, Nizhny Novgorod (Russian Federation)

    1995-09-01

    Peculiarities of integral reactor thermohydraulics in accidents are associated with presence of noncondensable gas in built-in pressurizer, absence of pumped ECCS, use of guard vessel for LOCAs localisation and passive RHRS through in-reactor HX`s. These features defined the main trends in experimental investigations and verification efforts for computer codes applied. The paper reviews briefly the performed experimental investigation of thermohydraulics of AST-500, VPBER600-type integral reactors. The characteristic of UROVEN/MB-3 code for LOCAs analysis in integral reactors and results of its verification are given. The assessment of RELAP5/mod3 applicability for accident analysis in integral reactor is presented.

  16. An efficient method for evaluating the effect of input parameters on the integrity of safety systems

    International Nuclear Information System (INIS)

    Tang, Zhang-Chun; Zuo, Ming J.; Xiao, Ningcong

    2016-01-01

    Safety systems are significant to reduce or prevent risk from potentially dangerous activities in industry. Probability of failure to perform its functions on demand (PFD) for safety system usually exhibits variation due to the epistemic uncertainty associated with various input parameters. This paper uses the complementary cumulative distribution function of the PFD to define the exceedance probability (EP) that the PFD of the system is larger than the designed value. Sensitivity analysis of safety system is further investigated, which focuses on the effect of the variance of an individual input parameter on the EP resulting from epistemic uncertainty associated with the input parameters. An available numerical technique called finite difference method is first employed to evaluate the effect, which requires extensive computational cost and needs to select a step size. To address these difficulties, this paper proposes an efficient simulation method to estimate the effect. The proposed method needs only an evaluation to estimate the effects corresponding to all input parameters. Two examples are used to demonstrate that the proposed method can obtain more accurate results with less computation time compared to reported methods. - Highlights: • We define a sensitivity index to measure effect of a parameter for safety system. • We analyze the physical meaning of the sensitivity index. • We propose an efficient simulation method to assess the sensitivity index. • We derive the formulations of this index for lognormal and beta distributions. • Results identify important parameters on exceedance probability of safety system.

  17. 24. MPA-seminar: safety and reliability of plant technology with special emphasis on integrity and life management. Vol. 1. Papers 1-27

    International Nuclear Information System (INIS)

    1999-01-01

    The first volume is dedicated to the safety and reliability of plant technology with special emphasis on the integrity and life management. The main topic in the volume is the contribution of nondestructive testing to the reactor safety from an international point of view. All 20 papers are separately analyzed for this database. (orig.)

  18. Study on systematic integration technology of design and safety assessment for HLW geological disposal. 2. Research document

    International Nuclear Information System (INIS)

    Ishihara, Yoshinao; Fukui, Hiroshi; Sagawa, Hiroshi; Matsunaga, Kenichi; Ito, Takaya; Kohanawa, Osamu; Kuwayama, Yuki

    2003-02-01

    The present study was carried out relating to basic design of the Geological Disposal Technology Integration System' that will be systematized as knowledge base for design analysis and safety assessment of HLW geological disposal system by integrating organically and hierarchically various technical information in three study field. The key conclusions are summarized as follows: (1) As referring to the current performance assessment report, the technical information for R and D program of HLW geological disposal system was systematized hierarchically based on summarized information in a suitable form between the work flow (work item) and processes/characteristic flow (process item). (2) As the result of the systematized technical information, database structure and system functions necessary for development and construction to the computer system were clarified in order to secure the relation between technical information and data set for assessment of HLW geological disposal system. (3) The control procedure for execution of various analysis code used by design and safety assessment in HLW geological disposal study was arranged possibility in construction of 'Geological Disposal Technology Integration System' after investigating the distributed computing technology. (author)

  19. The EUCLID/V1 Integrated Code for Safety Assessment of Liquid Metal Cooled Fast Reactors. Part 1: Basic Models

    Science.gov (United States)

    Mosunova, N. A.

    2018-05-01

    The article describes the basic models included in the EUCLID/V1 integrated code intended for safety analysis of liquid metal (sodium, lead, and lead-bismuth) cooled fast reactors using fuel rods with a gas gap and pellet dioxide, mixed oxide or nitride uranium-plutonium fuel under normal operation, under anticipated operational occurrences and accident conditions by carrying out interconnected thermal-hydraulic, neutronics, and thermal-mechanical calculations. Information about the Russian and foreign analogs of the EUCLID/V1 integrated code is given. Modeled objects, equation systems in differential form solved in each module of the EUCLID/V1 integrated code (the thermal-hydraulic, neutronics, fuel rod analysis module, and the burnup and decay heat calculation modules), the main calculated quantities, and also the limitations on application of the code are presented. The article also gives data on the scope of functions performed by the integrated code's thermal-hydraulic module, using which it is possible to describe both one- and twophase processes occurring in the coolant. It is shown that, owing to the availability of the fuel rod analysis module in the integrated code, it becomes possible to estimate the performance of fuel rods in different regimes of the reactor operation. It is also shown that the models implemented in the code for calculating neutron-physical processes make it possible to take into account the neutron field distribution over the fuel assembly cross section as well as other features important for the safety assessment of fast reactors.

  20. Development of the JNC geological disposal technical information integration system subjected for repository design and safety assessment

    International Nuclear Information System (INIS)

    Ishihara, Yoshinao; Ito, Takashi; Kobayashi, Shigeki; Neyama, Atsushi

    2004-02-01

    On this work, system manufacture about disposal technology and safety assessment field was performed towards construction of the JNC Geological Disposal Technical Information Integration System which systematized three fields of technical information acquired in investigation (site characteristic investigation) of geology environmental conditions, disposal technology (design of deep repository), and performance/safety assessment. The technical information database managed focusing on the technical information concerning individual research of an examination, analysis, etc. and the parameter set database managed focusing on the set up data set used in case of comprehensive evaluation are examined. In order to support and promote share and use of the technical information registered and managed by the database, utility functions, such as a technical information registration function, technical information search/browse function, analysis support function, and visualization function, are considered, and the system realized in these functions is built. The built system is installed in the server of JNC, and the functional check examination is carried out. (author)

  1. A Development Framework for Software Security in Nuclear Safety Systems: Integrating Secure Development and System Security Activities

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jaekwan; Suh, Yongsuk [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-02-15

    The protection of nuclear safety software is essential in that a failure can result in significant economic loss and physical damage to the public. However, software security has often been ignored in nuclear safety software development. To enforce security considerations, nuclear regulator commission recently issued and revised the security regulations for nuclear computer-based systems. It is a great challenge for nuclear developers to comply with the security requirements. However, there is still no clear software development process regarding security activities. This paper proposes an integrated development process suitable for the secure development requirements and system security requirements described by various regulatory bodies. It provides a three-stage framework with eight security activities as the software development process. Detailed descriptions are useful for software developers and licensees to understand the regulatory requirements and to establish a detailed activity plan for software design and engineering.

  2. Passive safety systems reliability and integration of these systems in nuclear power plant PSA

    International Nuclear Information System (INIS)

    La Lumia, V.; Mercier, S.; Marques, M.; Pignatel, J.F.

    2004-01-01

    Innovative nuclear reactor concepts could lead to use passive safety features in combination with active safety systems. A passive system does not need active component, external energy, signal or human interaction to operate. These are attractive advantages for safety nuclear plant improvements and economic competitiveness. But specific reliability problems, linked to physical phenomena, can conduct to stop the physical process. In this context, the European Commission (EC) starts the RMPS (Reliability Methods for Passive Safety functions) program. In this RMPS program, a quantitative reliability evaluation of the RP2 system (Residual Passive heat Removal system on the Primary circuit) has been realised, and the results introduced in a simplified PSA (Probabilistic Safety Assessment). The scope is to get out experience of definition of characteristic parameters for reliability evaluation and PSA including passive systems. The simplified PSA, using event tree method, is carried out for the total loss of power supplies initiating event leading to a severe core damage. Are taken into account: failures of components but also failures of the physical process involved (e.g. natural convection) by a specific method. The physical process failure probabilities are assessed through uncertainty analyses based on supposed probability density functions for the characteristic parameters of the RP2 system. The probabilities are calculated by MONTE CARLO simulation coupled to the CATHARE thermalhydraulic code. The yearly frequency of the severe core damage is evaluated for each accident sequence. This analysis has identified the influence of the passive system RP2 and propose a re-dimensioning of the RP2 system in order to satisfy the safety probabilistic objectives for reactor core severe damage. (authors)

  3. An integrated environment of software development and V and V for PLC based safety-critical systems

    International Nuclear Information System (INIS)

    Koo, Seo Ryong

    2005-02-01

    To develop and implement a safety-critical system, the requirements of the system must be analyzed thoroughly during the phases of a software development's life cycle because a single error in the requirements can generate serious software faults. We therefore propose an Integrated Environment (IE) approach for requirements which is an integrated approach that enables easy inspection by combining requirement traceability and effective use of a formal method. For the V and V tasks of requirements phase, our approach uses software inspection, requirement traceability, and formal specification with structural decomposition. Software inspection and the analysis of requirements traceability are the most effective methods of software V and V. Although formal methods are also considered an effective V and V activity, they are difficult to use properly in nuclear fields, as well as in other fields, because of their mathematical nature. We also propose another Integrated Environment (IE) for the design and implementation of safety-critical systems. In this study, a nuclear FED-style design specification and analysis (NuFDS) approach was proposed for PLC based safety-critical systems. The NuFDS approach is suggested in a straightforward manner for the effective and formal specification and analysis of software designs. Accordingly, the proposed NuFDS approach comprises one technique for specifying the software design and another for analyzing the software design. In addition, with the NuFDS approach, we can analyze the safety of software on the basis of fault tree synthesis. To analyze the design phase more effectively, we propose a technique of fault tree synthesis, along with a universal fault tree template for the architecture modules of nuclear software. Various tools have been needed to make software V and V more convenient. We therefore developed four kinds of computer-aided software engineering tools that could be used in accordance with the software's life cycle to

  4. Integrative Modeling of cap-rock Integrity in the Context of CO2 Storage: Evolution of Transport and Geochemical Properties and Impact on Performance and Safety Assessment

    International Nuclear Information System (INIS)

    Bildstein, O.; Credoz, A.; Jullien, M.; Kervevan, C.; Audigane, P.; Jacquemet, N.; Lagneau, V.; Delaplace, P.; Perfetti, E.

    2010-01-01

    The objective of the 'Geocarbone-INTEGRITE' project (2005-2008) was to develop a methodology to assess the integrity of the cap-rock involved in the geological storage of CO 2 . A specific work package of the project (WP5) was dedicated to the integration of (1) the phenomenology describing the evolution of the storage system with a focus on the mechanisms occurring in the cap-rock and at the interface with the cap-rock, and (2) the data obtained from the investigation of petrographical, geomechanical, and geochemical properties, before and after reaction with CO 2 -rich solutions, performed in the other work packages (WP1 to WP4). This knowledge was introduced in numerical models and specific safety scenarios were defined in order to assess the performance of the CO 2 storage system. The results of the modeling show that the injection of CO 2 can potentially have a significant effect on the cap-rock by changing the porosity due to the dissolution and precipitation of minerals, but that the impact is limited to a zone from several decimeters to several meters of the cap-rock close to the interface with the reservoir depending on whether the supercritical carbon dioxide (SC-CO 2 ) plume enters into the cap-rock and if fractures are present at this location. The methodology used in this project can be applied to a pilot site for the injection of CO 2 in the Paris Basin. A key aspect of the safety of such a facility will be to look at the coupling of geochemical alteration and the evolution of geomechanical properties in the short and medium terms (several hundreds of years). The challenge for the future will be to structure and apply the safety assessment methodology with an operational finality, in order to support the robustness of the transition step to CGS projects at the industrial scale. (authors)

  5. Comparing the cardiovascular therapeutic indices of glycopyrronium and tiotropium in an integrated rat pharmacokinetic, pharmacodynamic and safety model

    International Nuclear Information System (INIS)

    Trifilieff, Alexandre; Ethell, Brian T.; Sykes, David A.; Watson, Kenny J.; Collingwood, Steve; Charlton, Steven J.; Kent, Toby C.

    2015-01-01

    Long acting inhaled muscarinic receptor antagonists, such as tiotropium, are widely used as bronchodilator therapy for chronic obstructive pulmonary disease (COPD). Although this class of compounds is generally considered to be safe and well tolerated in COPD patients the cardiovascular safety of tiotropium has recently been questioned. We describe a rat in vivo model that allows the concurrent assessment of muscarinic antagonist potency, bronchodilator efficacy and a potential for side effects, and we use this model to compare tiotropium with NVA237 (glycopyrronium bromide), a recently approved inhaled muscarinic antagonist for COPD. Anaesthetized Brown Norway rats were dosed intratracheally at 1 or 6 h prior to receiving increasing doses of intravenous methacholine. Changes in airway resistance and cardiovascular function were recorded and therapeutic indices were calculated against the ED 50 values for the inhibition of methacholine-induced bronchoconstriction. At both time points studied, greater therapeutic indices for hypotension and bradycardia were observed with glycopyrronium (19.5 and 28.5 fold at 1 h; > 200 fold at 6 h) than with tiotropium (1.5 and 4.2 fold at 1 h; 4.6 and 5.5 fold at 6 h). Pharmacokinetic, protein plasma binding and rat muscarinic receptor binding properties for both compounds were determined and used to generate an integrated model of systemic M 2 muscarinic receptor occupancy, which predicted significantly higher M 2 receptor blockade at ED 50 doses with tiotropium than with glycopyrronium. In our preclinical model there was an improved safety profile for glycopyrronium when compared with tiotropium. - Highlights: • We use an in vivo rat model to study CV safety of inhaled muscarinic antagonists. • We integrate protein and receptor binding and PK of tiotropium and glycopyrrolate. • At ED 50 doses for bronchoprotection we model systemic M 2 receptor occupancy. • Glycopyrrolate demonstrates lower M 2 occupancy at

  6. An integrated software system for core design and safety analyses: Cascade-3D

    International Nuclear Information System (INIS)

    Wan De Velde, A.; Finnemann, H.; Hahn, T.; Merk, S.

    1999-01-01

    The new Siemens program system CASCADE-3D (Core Analysis and Safety Codes for Advanced Design Evaluation) links some of the most advanced code packages for in-core fuel management and accident analysis: SAV95, PANBOX/COBRA and RELAP5. Consequently by using CASCADE-3D the potential of modern fuel assemblies and in-core fuel management strategies can be much better utilized because safety margins which had been reduced due to conservative methods are now predicted more accurately. By this innovative code system the customers can now take full advantage of the recent progress in fuel assembly design and in-core fuel management. (authors)

  7. Improving food safety in the supply chain: Integrating traceability in production and distribution planning

    DEFF Research Database (Denmark)

    Grunow, Martin; Rong, Aiying; Akkerman, Renzo

    2008-01-01

    on production and distribution planning. Here, we develop a methodology for production and distribution planning in food supply chains which minimizes production and logistics costs and at the same time reduces food safety concerns, limits the size of potential recalls, and satisfies product quality...... with traceability from the viewpoint of information system development and technology development such as radio frequency identification (RFID) and DNA-based techniques. However, traceability and its implications for food safety are thus far not incorporated in the standard operations management literature...

  8. The integrated code system CASCADE-3D for advanced core design and safety analysis

    International Nuclear Information System (INIS)

    Neufert, A.; Van de Velde, A.

    1999-01-01

    The new program system CASCADE-3D (Core Analysis and Safety Codes for Advanced Design Evaluation) links some of Siemens advanced code packages for in-core fuel management and accident analysis: SAV95, PANBOX/COBRA and RELAP5. Consequently by using CASCADE-3D the potential of modern fuel assemblies and in-core fuel management strategies can be much better utilized because safety margins which had been reduced due to conservative methods are now predicted more accurately. By this innovative code system the customers can now take full advantage of the recent progress in fuel assembly design and in-core fuel management.(author)

  9. In Vivo Transplantation of Enteric Neural Crest Cells into Mouse Gut; Engraftment, Functional Integration and Long-Term Safety.

    Directory of Open Access Journals (Sweden)

    Julie E Cooper

    Full Text Available Enteric neuropathies are severe gastrointestinal disorders with unsatisfactory outcomes. We aimed to investigate the potential of enteric neural stem cell therapy approaches for such disorders by transplanting mouse enteric neural crest cells (ENCCs into ganglionic and aganglionic mouse gut in vivo and analysing functional integration and long-term safety.Neurospheres generated from yellow fluorescent protein (YFP expressing ENCCs selected from postnatal Wnt1-cre;R26R-YFP/YFP murine gut were transplanted into ganglionic hindgut of wild-type littermates or aganglionic hindgut of Ednrbtm1Ywa mice (lacking functional endothelin receptor type-B. Intestines were then assessed for ENCC integration and differentiation using immunohistochemistry, cell function using calcium imaging, and long-term safety using PCR to detect off-target YFP expression.YFP+ ENCCs engrafted, proliferated and differentiated into enteric neurons and glia within recipient ganglionic gut. Transplanted cells and their projections spread along the endogenous myenteric plexus to form branching networks. Electrical point stimulation of endogenous nerve fibres resulted in calcium transients (F/F0 = 1.16 ± 0.01;43 cells, n = 6 in YFP+ transplanted ENCCs (abolished with TTX. Long-term follow-up (24 months showed transplanted ENCCs did not give rise to tumours or spread to other organs (PCR negative in extraintestinal sites. In aganglionic gut ENCCs similarly spread and differentiated to form neuronal and glial networks with projections closely associated with endogenous neural networks of the transition zone.Transplanted ENCCs successfully engrafted into recipient ganglionic and aganglionic gut showing appropriate spread, localisation and, importantly, functional integration without any long-term safety issues. This study provides key support for the development and use of enteric neural stem cell therapies.

  10. Management of radioactive waste gases from PET radiopharmaceutical synthesis using cost effective capture systems integrated with a cyclotron safety system.

    Science.gov (United States)

    Stimson, D H R; Pringle, A J; Maillet, D; King, A R; Nevin, S T; Venkatachalam, T K; Reutens, D C; Bhalla, R

    2016-09-01

    The emphasis on the reduction of gaseous radioactive effluent associated with PET radiochemistry laboratories has increased. Various radioactive gas capture strategies have been employed historically including expensive automated compression systems. We have implemented a new cost-effective strategy employing gas capture bags with electronic feedback that are integrated with the cyclotron safety system. Our strategy is suitable for multiple automated 18 F radiosynthesis modules and individual automated 11 C radiosynthesis modules. We describe novel gas capture systems that minimize the risk of human error and are routinely used in our facility.

  11. WWER-440/V-230 Confinement modernization to upgrade the critical safety function 'Containment integrity' in case of severe accident

    International Nuclear Information System (INIS)

    Sartmadjiev, A.

    1999-01-01

    In this lecture the WWER-440/V-230 confinement modernization to upgrade the critical safety function 'Containment integrity' in case of severe accident is presented. There are discussed: design limitations of the location system; consequence from these design limitations; a few confinement reconstruction concepts of this type of units worldwide; and purpose of the confinement reconstruction - to improve significantly the original design, ensuring (1) localization for all possible primary breaks and (2) limitation of the radiological consequences for the personnel, the population and the environment below the regulatory requirements

  12. Validation of a functional model for integration of safety into process system design

    DEFF Research Database (Denmark)

    Wu, J.; Lind, M.; Zhang, X.

    2015-01-01

    with the process system functionalities as required for the intended safety applications. To provide the scientific rigor and facilitate the acceptance of qualitative modelling, this contribution focuses on developing a scientifically based validation method for functional models. The Multilevel Flow Modeling (MFM...

  13. An integrated approach for improving occupational health and safety management: the voluntary protection program in Taiwan.

    Science.gov (United States)

    Su, Teh-Sheng; Tsai, Way-Yi; Yu, Yi-Chun

    2005-05-01

    A voluntary compliance program for occupational health and safety management, Voluntary Protection Programs (VPP), was implemented with a strategy of cooperation and encouragement in Taiwan. Due to limitations on increasing the human forces of inspection, a regulatory-based guideline addressing the essence of Occupational Health and Safety Management Systems (OHSMS) was promulgated, which combined the resources of third parties and insurance providers to accredit a self-improving worksite with the benefits of waived general inspection and a merit contributing to insurance premium payment reduction. A designated institute accepts enterprise's applications, performs document review and organizes the onsite inspection. A final review committee of Council of Labor Affairs (CLA) confers a two-year certificate on an approved site. After ten years, the efforts have shown a dramatic reduction of occupational injuries and illness in the total number of 724 worksites granted certification. VPP worksites, in comparison with all industries, had 49% lower frequency rate in the past three years. The severity rate reduction was 80% in the same period. The characteristics of Taiwan VPP program and international occupational safety and health management programs are provided. A Plan-Do-Check-Act management cycle was employed for pursuing continual improvements to the culture fostered. The use of a quantitative measurement for assessing the performance of enterprises' occupational safety and health management showed the efficiency of the rating. The results demonstrate that an employer voluntary protection program is a promising strategy for a developing country.

  14. Integration of transport and handling equipment at CERN criteria to satisfy operational needs and safety aspects

    CERN Document Server

    Bertone, C; CERN. Geneva. TS Department

    2004-01-01

    Within the last 4 years TS-IC-HM (former ST-HM group) integrated about 150 transport and handling supplies including 29 cranes, 20 fork lift trucks, 60 tunnel vehicles. Most of these are standardised supplies, but very often special functionality has been implemented and the complexity of the equipment has been increased. With the Rocla cryo-dipol transporters even prototype equipment was integrated that had been specially designed for CERN. This paper discusses the differences regarding the actions that have to be performed when the different kind of equipment have to be integrated.

  15. Integrated Reconfigurable Aero and Propulsion Control for Improved Flight Safety of Commercial Aircraft, Phase I

    Data.gov (United States)

    National Aeronautics and Space Administration — The main objective of this project is to develop and test a novel innovative Integrated Reconfigurable Aero (i) Adaptive control design for the case of aero-only...

  16. Modal Analysis of In-Wheel Motor-Driven Electric Vehicle Based on Bond Graph Theory

    Directory of Open Access Journals (Sweden)

    Di Tan

    2017-01-01

    Full Text Available A half-car vibration model of an electric vehicle driven by rear in-wheel motors was developed using bond graph theory and the modular modeling method. Based on the bond graph model, modal analysis was carried out to study the vibration characteristics of the electric vehicle. To verify the effectiveness of the established model, the results were compared to ones computed on the ground of modal analysis and Newton equations. The comparison shows that the vibration model of the electric vehicle based on bond graph theory not only is able to better compute the natural frequency but also can easily determine the deformation mode, momentum mode, and other isomorphism modes and describe the dynamic characteristics of an electric vehicle driven by in-wheel motors more comprehensively than other modal analysis methods.

  17. 24. MPA-seminar: safety and reliability of plant technology with special emphasis on integrity and life management. Vol. 2. Papers 28-63

    International Nuclear Information System (INIS)

    1999-01-01

    The second volume is dedicated to the safety and reliability of plant technology with special emphasis on the integrity and life management. The following topics are discussed: 1. Integrity of vessels, pipes and components. 2. Fracture mechanics. 3. Measures for the extension of service life, and 4. Online Monitoring. All 30 contributions are separately analyzed for this database. (orig.)

  18. Comparison of three small-break loss-of-coolant accident tests with different break locations using the system-integrated modular advanced reactor-integral test loop facility to estimate the safety of the smart design

    OpenAIRE

    Hwang Bae; Dong Eok Kim; Sung-Uk Ryu; Sung-Jae Yi; Hyun-Sik Park

    2017-01-01

    Three small-break loss-of-coolant accident (SBLOCA) tests with safety injection pumps were carried out using the integral-effect test loop for SMART (System-integrated Modular Advanced ReacTor), i.e., the SMART-ITL facility. The types of break are a safety injection system line break, shutdown cooling system line break, and pressurizer safety valve line break. The thermal–hydraulic phenomena show a traditional behavior to decrease the temperature and pressure whereas the local phenomena are s...

  19. MTR and PWR/PHWR in-pile loop safety in integration with the operation of multipurpose reactor - GAS

    International Nuclear Information System (INIS)

    Suharno; Aji, Bintoro; Sugiyanto; Rohman, Budi; Zarkasi, Amin S.; Giarno

    1998-01-01

    MTR and PWR/PHWR In-Pile Loop safety analysis in integration with the operation of Multipurpose Reactor - Gas has been carried out and completed. The assessment is emphasized on the function of the interface systems from the dependence of the operation and the evaluation to the possibility of leakage or failure of the in-pile part inside the reactor pool and reactor core. The analysis is refers to the logic function of the interface system and the possibility of leakage or failure of the in-pile part inside reactor pool and reactor core to consider the integrity of the core qualitatively. The results show that in normal and in transient conditions , the interface system meet the function requirement in safe integrated operation of in-pile loop and reactor. And the results of the possibility analysis of the leakage shows that the possibility based on mechanically assessment is very low and the impact to core integrity is nothing or can be eliminated. The possible position for leakage is on the flen on which one meter above the top level of the core, therefore no influence of leakage to the core

  20. The role of structural integrity in liquid metal fast breeder reactor safety

    International Nuclear Information System (INIS)

    Holmes, J.A.G.

    1982-01-01

    Extensive studies have demonstrated the favourable safety characteristics of liquid metal fast breeder reactors, which are attributable to both their inherent features and the engineered safeguards which are included. This requires demonstration that there is no risk of sudden catastrophic failure of the core support system allowing the core to drop off the control rods to give a prompt critical reactivity excursion. An important part of our work in support of the safety case for the U.K. Commercial Demonstration Fast Reactor is to demonstrate that such a failure is virtually incredible. This covers design features, study of the fracture behaviour of stainless steel structures, and inspection and monitoring during fabrication and service. The paper gives a broad description of the relevant design features and supporting work programme

  1. Proceedings of the workshop on integral experiment covariance data for critical safety validation

    Energy Technology Data Exchange (ETDEWEB)

    Stuke, Maik (ed.)

    2016-04-15

    For some time, attempts to quantify the statistical dependencies of critical experiments and to account for them properly in validation procedures were discussed in the literature by various groups. Besides the development of suitable methods especially the quality and modeling issues of the freely available experimental data are in the focus of current discussions, carried out for example in the Expert Group on Uncertainty Analysis for Criticality Safety Assessment (UACSA) of the OECD-NEA Nuclear Science Committee. The same committee compiles and publishes also the freely available experimental data in the International Handbook of Evaluated Criticality Safety Benchmark Experiments. Most of these experiments were performed as series and might share parts of experimental setups leading to correlated results. The quality of the determination of these correlations and the underlying covariance data depend strongly on the quality of the documentation of experiments.

  2. Proceedings of the workshop on integral experiment covariance data for critical safety validation

    International Nuclear Information System (INIS)

    Stuke, Maik

    2016-04-01

    For some time, attempts to quantify the statistical dependencies of critical experiments and to account for them properly in validation procedures were discussed in the literature by various groups. Besides the development of suitable methods especially the quality and modeling issues of the freely available experimental data are in the focus of current discussions, carried out for example in the Expert Group on Uncertainty Analysis for Criticality Safety Assessment (UACSA) of the OECD-NEA Nuclear Science Committee. The same committee compiles and publishes also the freely available experimental data in the International Handbook of Evaluated Criticality Safety Benchmark Experiments. Most of these experiments were performed as series and might share parts of experimental setups leading to correlated results. The quality of the determination of these correlations and the underlying covariance data depend strongly on the quality of the documentation of experiments.

  3. Research program Integrity of Components (FKS). A substantial contribution to component safety

    International Nuclear Information System (INIS)

    Kussmaul, K.; Roos, E.; Foehl, J.

    1998-01-01

    The main objectives pursued are: (a) verify the quality of reactor pressure vessels in existing LWR-type reactors, and (b) quantify the safety margin using both specified and non-specified materials and welds. On the basis of knowledge obtained through earlier programmes, the research project was to examine in particular deviations from the specified materials properties, for more exact quantification of the safety margin before RPV failure. There are three major factors influencing the component performance until failure, which are aggregate material fatigue, flaws, loading conditions, and the research work was to focus on the materials properties. An item of main interest was to assess the impact of long service life on the materials properties, assuming particularly unfavourable boundary conditions for materials properties and operational loads. (orig./CB) [de

  4. Integrated protection model: ISO 45001 as a future of safety and health standards

    Directory of Open Access Journals (Sweden)

    Živković Snežana

    2015-01-01

    Full Text Available Along with the increase in awareness of the importance of human resources and their contribution to the value of the organization, there is a growing awareness of the need for their management. The fact that modern society prescribes by the law that organizations must identify dangers and hazards, risk level that may arise, as well as their management and implementation of consistent measures to reduce their impact, shows the importance that is attributed to this issue. For the effective implementation of laws in the field of health and safety at work and other necessary protective measures, there has been a need for a systematic approach to management in this area. Systematic approach to management in the field of health and safety at work ensures the implementation of all measures necessary for the safe operation thus protecting both employees and organization. This systematic approach is reflected in the current standard OHSAS 18001, which aims to establish control over the risks that carry harmful potentials, and thus ensuring the continuity of operation of the organization. The focus of the scientific community which is actively working on improving the existing standards in the field of safety and health of employees is focused on the upcoming standard that will replace OHSAS 18001. The upcoming standard places a greater emphasis on the risk management and the ongoing assessment of risks and opportunities to prevent or reduce side effects. The innovations in this standard are reflected in the strengthening of the role of top management and top management as well as in the context of the 'organization' itself. ISO 45001 provides for active participation of management in all processes of health and safety at work and tends to reduce the usage of process of delegated responsibility to one manager, while, on the other hand, the organization looks at the broader, i.e., the requirements of the wider community are taken into account.

  5. Representing the Fuzzy improved risk graph for determination of optimized safety integrity level in industrial setting

    Directory of Open Access Journals (Sweden)

    Z. Qorbali

    2013-12-01

    .Conclusion: as a result of establishing the presented method, identical levels in conventional risk graph table are replaced with different sublevels that not only increases the accuracy in determining the SIL, but also elucidates the effective factor in improving the safety level and consequently saves time and cost significantly. The proposed technique has been employed to develop the SIL of Tehran Refinery ISOMAX Center. IRG and FIRG results have been compared to clarify the efficacy and importance of the proposed method

  6. DASS: A decision aid integrating the safety parameter display system and emergency functional recovery procedures. Final report

    International Nuclear Information System (INIS)

    Johnson, S.E.

    1984-08-01

    Using a stand-alone developmental test-bed consisting of a minicomputer and a high-resolution color graphics computer, displays and supporting software incorporating advanced on-line decision-aid concepts were developed and evaluated. The advanced concepts embodied in displays designed for the operating crew of a PWR plant include: (1) an integrated display format which supports a top-down approach to problem detection, recovery planning, and control; (2) introduction of nonobservable plant parameters derived from first principles mass and energy balances as part of the displayed information; and (3) systematic processing and display of key success path (plant safety system) attributes. The prototype system, referred to as the PWR-DASS (Disturbance Analysis and Surveillance System), consists of 18 displays targeted for principal use by the control room systems manager. PWR-DASS was conceived to fulfill an operational void not fully supported by safety parameter display systems or reformulated emergency procedure guidelines. The results from the evaluation by licensed operators suggest that organization and display of desired critical safety function and success path information as incorporated in the PWR-DASS prototype can support the systems manager's overview. The results also point to the need for several refinements required for a field grade system, and to the need for a simulator-based evaluation of the prototype or its successor. (author)

  7. Qualification of integrated tool environments (QUITE) for the development of computer-based safety systems in NPP

    International Nuclear Information System (INIS)

    Miedl, Horst

    2004-01-01

    In NPP I et C systems are back fitted meanwhile increasingly by computer-based systems (I et C platforms). The corresponding safety functions are implemented by software, and this software is developed, configured and administrated with the help of integrated tool environments (ITE). An ITE offers a set of services which are used to construct an I et C system and consist typically of software packages for project control and documentation, specification and design, automatic code generation and so on. Commercial ITE are not necessarily conceived and qualified (type-tested) for nuclear specific applications but are used - and will increasingly be used - for the implementation of nuclear safety related I et C systems. Therefor, it is necessary to qualify commercial ITE with respect to their influence on the quality of the target system for each I et C platform (dependent on the safety category of the target system). Examples for commercial ITEs are I et C platforms like SPINLINE 3, TELEPERM XP, Common Q, TRICON, etc. (Author)

  8. On integration and innovation of sino-foreign safety culture in Haiyang AP1000 Project

    International Nuclear Information System (INIS)

    Li Ruipu; Song Fengwei

    2010-01-01

    The undergoing Haiyang Nuclear Power Plant is not only introducing the top-advanced AP1000 nuclear technology, but also the mature HSE management system from U.S.A. It's very important for both sides to communicate, comprehend and acculturation of both different culture. After over 1 year discussion and practice, the experts of Westinghouse Consortium and Chinese HSE engineers have established an distinctive safety culture of AP1000 Project initially, demonstrating the followings: Exemplary actions of the expat experts and the SNPTC leaders, the high level standard HSE procedures, HSE audit, various training, HSE inspection all-around, the safety performance assessment for prospective index, JHA/JSA , emergency system, humanism rewards and punishment etc.. Haiyang SPMO has made Three-Step master plan for AP1000 project HSE Routine by analysis the site problems and the difference between Chinese and American, that is, from 2008 to 2020, when nuclear power achieve to independent, safety culture of Haiyang AP1000 will change from 'dependent' to 'independent', until the last 'interdependent'. (authors)

  9. Motivating safety belt use at a community hospital: an effective integration of incentive and commitment strategies.

    Science.gov (United States)

    Nimmer, J G; Geller, E S

    1988-06-01

    An effective hospital-based safety-belt program incorporated several advantages over prior attempts to increase safety belt use, including (a) the use of indigenous staff as program sponsors, coordinators, and delivery agents; (b) a yearlong program evaluation; and (c) a combination of extrinsic incentives and intrinsic commitment. To be eligible for a weekly $5, employees met the following contingencies: (a) signed a pledge card; (b) displayed the signed pledge card in their vehicle; and (c) wore a safety belt. Overall, belt use increased from a 2-week baseline mean of 15.6% to 34.7% during the 6-month intervention, and decreased to 25.6% at withdrawal. For the pledge card signers (n = 188) and the nonsigners (n = 533), belt use increased from baseline means of 29.4% and 11.8% to intervention use rates of 75.1 and 17.7%, respectively. Withdrawal and 4-month follow-up use rates were 56.0% and 44.9% for the Pledge group, and 17.2% and 22.1% for the Nonpledge group.

  10. INTEGRAL BENCHMARKS AVAILABLE THROUGH THE INTERNATIONAL REACTOR PHYSICS EXPERIMENT EVALUATION PROJECT AND THE INTERNATIONAL CRITICALITY SAFETY BENCHMARK EVALUATION PROJECT

    International Nuclear Information System (INIS)

    J. Blair Briggs; Lori Scott; Enrico Sartori; Yolanda Rugama

    2008-01-01

    Interest in high-quality integral benchmark data is increasing as efforts to quantify and reduce calculational uncertainties accelerate to meet the demands of next generation reactor and advanced fuel cycle concepts. The International Reactor Physics Experiment Evaluation Project (IRPhEP) and the International Criticality Safety Benchmark Evaluation Project (ICSBEP) continue to expand their efforts and broaden their scope to identify, evaluate, and provide integral benchmark data for method and data validation. Benchmark model specifications provided by these two projects are used heavily by the international reactor physics, nuclear data, and criticality safety communities. Thus far, 14 countries have contributed to the IRPhEP, and 20 have contributed to the ICSBEP. The status of the IRPhEP and ICSBEP is discussed in this paper, and the future of the two projects is outlined and discussed. Selected benchmarks that have been added to the IRPhEP and ICSBEP handbooks since PHYSOR-06 are highlighted, and the future of the two projects is discussed

  11. INTEGRAL BENCHMARKS AVAILABLE THROUGH THE INTERNATIONAL REACTOR PHYSICS EXPERIMENT EVALUATION PROJECT AND THE INTERNATIONAL CRITICALITY SAFETY BENCHMARK EVALUATION PROJECT

    Energy Technology Data Exchange (ETDEWEB)

    J. Blair Briggs; Lori Scott; Enrico Sartori; Yolanda Rugama

    2008-09-01

    Interest in high-quality integral benchmark data is increasing as efforts to quantify and reduce calculational uncertainties accelerate to meet the demands of next generation reactor and advanced fuel cycle concepts. The International Reactor Physics Experiment Evaluation Project (IRPhEP) and the International Criticality Safety Benchmark Evaluation Project (ICSBEP) continue to expand their efforts and broaden their scope to identify, evaluate, and provide integral benchmark data for method and data validation. Benchmark model specifications provided by these two projects are used heavily by the international reactor physics, nuclear data, and criticality safety communities. Thus far, 14 countries have contributed to the IRPhEP, and 20 have contributed to the ICSBEP. The status of the IRPhEP and ICSBEP is discussed in this paper, and the future of the two projects is outlined and discussed. Selected benchmarks that have been added to the IRPhEP and ICSBEP handbooks since PHYSOR’06 are highlighted, and the future of the two projects is discussed.

  12. Safety demonstration tests on pressure rise in ventilation system and blower integrity of a fuel-reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Takada, Junichi; Suzuki, Motoe; Tsukamoto, Michio; Koike, Tadao; Nishio, Gunji [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1996-12-01

    In JAERI, the demonstration test was carried out as a part of safety researches of the fuel-reprocessing plant using a large-scale facility consist of cells, ducts, dumpers, HEPA filters and a blower, when an explosive burning due to a rapid reaction of thermal decomposition for solvent/nitric acid occurs in a cell of the reprocessing plant. In the demonstration test, pressure response propagating through the facility was measured under a blowing of air from a pressurized tank into the cell in the facility to elucidate an influence of pressure rise in the ventilation system. Consequently, effective pressure decrease in the facility was given by a configuration of cells and ducts in the facility. In the test, transient responses of HEPA filters and the blower by the blowing of air were also measured to confirm the integrity. So that, it is confirmed that HEPA filters and the blower under pressure loading were sufficient to maintain the integrity. The content described in this report will contribute to safety assessment of the ventilation system in the event of explosive burning in the reprocessing plant. (author)

  13. Quality and safety of integrated community case management of malaria using rapid diagnostic tests and pneumonia by community health workers.

    Science.gov (United States)

    Hamer, Davidson H; Brooks, Erin Twohig; Semrau, Katherine; Pilingana, Portipher; MacLeod, William B; Siazeele, Kazungu; Sabin, Lora L; Thea, Donald M; Yeboah-Antwi, Kojo

    2012-03-01

    To assess the quality and safety of having community health workers (CHWs) in rural Zambia use rapid diagnostic tests (RDTs) and provide integrated management of malaria and pneumonia. In the context of a cluster-randomized controlled trial of two models for community-based management of malaria and/or non-severe pneumonia in children under 5 years old, CHWs in the intervention arm were trained to use RDTs, follow a simple algorithm for classification and treat malaria with artemether-lumefantrine (AL) and pneumonia with amoxicillin. CHW records were reviewed to assess the ability of the CHWs to appropriately classify and treat malaria and pneumonia, and account for supplies. Patients were also followed up to assess treatment safety. During the 12-month study, the CHWs evaluated 1017 children with fever and/or fast/difficult breathing and performed 975 RDTs. Malaria and/or pneumonia were appropriately classified 94-100% of the time. Treatment based on disease classification was correct in 94-100% of episodes. Supply management was excellent with over 98% of RDTs, amoxicillin, and AL properly accounted for. The use of RDTs, amoxicillin, and AL was associated with few minor adverse events. Most febrile children (90%) with negative RDT results recovered after being treated with an antipyretic alone. Volunteer CHWs in rural Zambia are capable of providing integrated management of malaria and pneumonia to children safely and at high quality.

  14. Assuring the safety of genetically modified (GM) foods: the importance of an holistic, integrative approach.

    Science.gov (United States)

    Cockburn, Andrew

    2002-09-11

    Genes change continuously by natural mutation and recombination enabling man to select and breed crops having the most desirable traits such as yield or flavour. Genetic modification (GM) is a recent development which allows specific genes to be identified, isolated, copied and inserted into other plants with a high level of specificity. The food safety considerations for GM crops are basically the same as those arising from conventionally bred crops, very few of which have been subject to any testing yet are generally regarded as being safe to eat. In contrast a rigorous safety testing paradigm has been developed for GM crops, which utilises a systematic, stepwise and holistic approach. The resultant science based process, focuses on a classical evaluation of the toxic potential of the introduced novel trait and the wholesomeness of the transformed crop. In addition, detailed consideration is given to the history and safe use of the parent crop as well as that of the gene donor. The overall safety evaluation is conducted under the concept known as substantial equivalence which is enshrined in all international crop biotechnology guidelines. This provides the framework for a comparative approach to identify the similarities and differences between the GM product and its comparator which has a known history of safe use. By building a detailed profile on each step in the transformation process, from parent to new crop, and by thoroughly evaluating the significance from a safety perspective, of any differences that may be detected, a very comprehensive matrix of information is constructed which enables the conclusion as to whether the GM crop, derived food or feed is as safe as its traditional counterpart. Using this approach in the evaluation of more than 50 GM crops which have been approved worldwide, the conclusion has been that foods and feeds derived from genetically modified crops are as safe and nutritious as those derived from traditional crops. The lack of

  15. Comparison of three small-break loss-of-coolant accident tests with different break locations using the system-integrated modular advanced reactor-integral test loop facility to estimate the safety of the smart design

    Directory of Open Access Journals (Sweden)

    Hwang Bae

    2017-08-01

    Full Text Available Three small-break loss-of-coolant accident (SBLOCA tests with safety injection pumps were carried out using the integral-effect test loop for SMART (System-integrated Modular Advanced ReacTor, i.e., the SMART-ITL facility. The types of break are a safety injection system line break, shutdown cooling system line break, and pressurizer safety valve line break. The thermal–hydraulic phenomena show a traditional behavior to decrease the temperature and pressure whereas the local phenomena are slightly different during the early stage of the transient after a break simulation. A safety injection using a high-pressure pump effectively cools down and recovers the inventory of a reactor coolant system. The global trends show reproducible results for an SBLOCA scenario with three different break locations. It was confirmed that the safety injection system is robustly safe enough to protect from a core uncovery.

  16. Comparison of three small-break loss-of-coolant accident tests with different break locations using the system-integrated modular advanced reactor-integral test loop facility to estimate the safety of the smart design

    Energy Technology Data Exchange (ETDEWEB)

    Bae, Hwang; Ryu, Sung Uk; Yi, Sung Jae; Park, Hyun Sik [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kim, Dong Eok [Dept. of Precision Mechanical Engineering, Kyungpook National University, Sangju (Korea, Republic of)

    2017-08-15

    Three small-break loss-of-coolant accident (SBLOCA) tests with safety injection pumps were carried out using the integral-effect test loop for SMART (System-integrated Modular Advanced ReacTor), i.e., the SMART-ITL facility. The types of break are a safety injection system line break, shutdown cooling system line break, and pressurizer safety valve line break. The thermal–hydraulic phenomena show a traditional behavior to decrease the temperature and pressure whereas the local phenomena are slightly different during the early stage of the transient after a break simulation. A safety injection using a high-pressure pump effectively cools down and recovers the inventory of a reactor coolant system. The global trends show reproducible results for an SBLOCA scenario with three different break locations. It was confirmed that the safety injection system is robustly safe enough to protect from a core uncovery.

  17. 77 FR 72435 - Pipeline Safety: Using Meaningful Metrics in Conducting Integrity Management Program Evaluations

    Science.gov (United States)

    2012-12-05

    ... effectiveness of their integrity management programs. Program evaluation is one of the key required program... activities that are in place to control risk. These measures indicate how well an operator is implementing... outcome is being achieved or not, despite the risk control activities in place. Failure Measures that...

  18. Managing structural design through integrated models and obtaining increased safety and economy

    International Nuclear Information System (INIS)

    Diaz, B.E.; Thomaz, E.C.S.

    1987-01-01

    The use of large finite element (FE) models for the design of reinforced concrete elements in nuclear power plants will be treated. For this technique a set of computer programs is necessary, since the amount of data is very large. With this design method a series of advantages is obtained such as: reduction of reinforcing steel expenditure, increase of safety through a better representation of the structures, an adequate control of the calculation due to the transparent method of design, reduction of design time due to the automatic computation and so on. (author)

  19. DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 2: Appendices

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-05-01

    This volume contains the appendices that provide additional environment, safety, and health (ES and H) information to complement Volume 1 of this Standard. Appendix A provides a set of candidate DOE ES and H directives and external regulations, organized by hazard types that may be used to identify potentially applicable directives to a specific facility disposition activity. Appendix B offers examples and lessons learned that illustrate implementation of ES and H approaches discussed in Section 3 of Volume 1. Appendix C contains ISMS performance expectations to guide a project team in developing and implementing an effective ISMS and in developing specific performance criteria for use in facility disposition. Appendix D provides guidance for identifying potential Applicable or Relevant and Appropriate Requirements (ARARs) when decommissioning facilities fall under the Comprehensive Environmental Response, Compensation, Liability Act (CERCLA) process. Appendix E discusses ES and H considerations for dispositioning facilities by privatization. Appendix F is an overview of the WSS process. Appendix G provides a copy of two DOE Office of Nuclear Safety Policy and Standards memoranda that form the bases for some of the guidance discussed within the Standard. Appendix H gives information on available hazard analysis techniques and references. Appendix I provides a supplemental discussion to Sections 3.3.4, Hazard Baseline Documentation, and 3.3.6, Environmental Permits. Appendix J presents a sample readiness evaluation checklist.

  20. Nuclear Power Plant Life Management - Challenges and Proposal for a Unified Model Integrating Safety and Economics

    International Nuclear Information System (INIS)

    Contri, Paolo; Elsing, Bernhard

    2011-01-01

    In recent years many electric utilities and nuclear power plants adopted policies for improved coordination of both safety and non-safety programs, called plant life management (PLIM), also in view on plant life extension programs, but mainly for an optimisation of operating costs. The implementation of PLIM programs has followed many different approaches, being intrinsically dependent on the national regulatory framework and technical traditions. In Countries with some experience, the PLIM program proved very convenient, especially when coupled with Maintenance, Surveillance an Inspection (MS and I) optimization: average savings are reported in the range of 20-30% of total (maintenance) costs. A unified European model for PLIM was developed at the JRC-Institute for Energy with the support of a network of stakeholders (SENUF), and validated at some EU nuclear plants. This paper provides a summary of the model features, the result of its validation at some plants and summarises the perceived scientific/technological challenges on which JRC proposes to focus, based upon its competencies and skills, having in mind both the European and world-wide context and its potential evolution. (author)

  1. DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 2: Appendices

    International Nuclear Information System (INIS)

    1998-05-01

    This volume contains the appendices that provide additional environment, safety, and health (ES and H) information to complement Volume 1 of this Standard. Appendix A provides a set of candidate DOE ES and H directives and external regulations, organized by hazard types that may be used to identify potentially applicable directives to a specific facility disposition activity. Appendix B offers examples and lessons learned that illustrate implementation of ES and H approaches discussed in Section 3 of Volume 1. Appendix C contains ISMS performance expectations to guide a project team in developing and implementing an effective ISMS and in developing specific performance criteria for use in facility disposition. Appendix D provides guidance for identifying potential Applicable or Relevant and Appropriate Requirements (ARARs) when decommissioning facilities fall under the Comprehensive Environmental Response, Compensation, Liability Act (CERCLA) process. Appendix E discusses ES and H considerations for dispositioning facilities by privatization. Appendix F is an overview of the WSS process. Appendix G provides a copy of two DOE Office of Nuclear Safety Policy and Standards memoranda that form the bases for some of the guidance discussed within the Standard. Appendix H gives information on available hazard analysis techniques and references. Appendix I provides a supplemental discussion to Sections 3.3.4, Hazard Baseline Documentation, and 3.3.6, Environmental Permits. Appendix J presents a sample readiness evaluation checklist

  2. Integrated Delivery of Quality, Safety and Environment through Road Sector Procurement: The Case of Public Sector Agencies in Ghana

    Directory of Open Access Journals (Sweden)

    Abdul-Majeed Mahamadu

    2015-01-01

    Full Text Available Poor quality, safety and environmental (QSE performance within Ghana's road sector has been cited as a major challenge in the procurement of infrastructure. This study evaluates the applicability and level of integrated consideration of QSE in the delivery of roads through procurement by public sector agencies in Ghana. Integrated delivery is explored on the basis of theoretical and empirical evidence of an existing synergistic relationship among QSE in the management and delivery of projects. A mixed methodological design was adopted to investigate two public road agencies through a questionnaire survey and interviews of technical staff with procurement responsibilities. This was done concurrently with soliciting professional perspectives on the subject. Procurement is widely regarded as paramount to the delivery of better QSE in the Ghana road sector. However, the level of synergistic consideration is low, which is attributable to an over-reliance on traditional procurement arrangements as a result of non-supportive local procurement regulatory frameworks. It is further established that a general lack of know-how and experience in the use of modern and integrated procurement arrangements prevent effective management and realisation of QSE beyond the current focus on time and cost through procurement processes within public road sector agencies.

  3. Epistemic and aleatory uncertainties in integrated deterministic and probabilistic safety assessment: Tradeoff between accuracy and accident simulations

    International Nuclear Information System (INIS)

    Karanki, D.R.; Rahman, S.; Dang, V.N.; Zerkak, O.

    2017-01-01

    The coupling of plant simulation models and stochastic models representing failure events in Dynamic Event Trees (DET) is a framework used to model the dynamic interactions among physical processes, equipment failures, and operator responses. The integration of physical and stochastic models may additionally enhance the treatment of uncertainties. Probabilistic Safety Assessments as currently implemented propagate the (epistemic) uncertainties in failure probabilities, rates, and frequencies; while the uncertainties in the physical model (parameters) are not propagated. The coupling of deterministic (physical) and probabilistic models in integrated simulations such as DET allows both types of uncertainties to be considered. However, integrated accident simulations with epistemic uncertainties will challenge even today's high performance computing infrastructure, especially for simulations of inherently complex nuclear or chemical plants. Conversely, intentionally limiting computations for practical reasons would compromise accuracy of results. This work investigates how to tradeoff accuracy and computations to quantify risk in light of both uncertainties and accident dynamics. A simple depleting tank problem that can be solved analytically is considered to examine the adequacy of a discrete DET approach. The results show that optimal allocation of computational resources between epistemic and aleatory calculations by means of convergence studies ensures accuracy within a limited budget. - Highlights: • Accident simulations considering uncertainties require intensive computations. • Tradeoff between accuracy and accident simulations is a challenge. • Optimal allocation between epistemic & aleatory computations ensures the tradeoff. • Online convergence gives an early indication of computational requirements. • Uncertainty propagation in DDET is examined on a tank problem solved analytically.

  4. The Neuroergonomics of Aircraft Cockpits: The Four Stages of Eye-Tracking Integration to Enhance Flight Safety

    Directory of Open Access Journals (Sweden)

    Vsevolod Peysakhovich

    2018-02-01

    Full Text Available Commercial aviation is currently one of the safest modes of transportation; however, human error is still one major contributing cause of aeronautical accidents and incidents. One promising avenue to further enhance flight safety is Neuroergonomics, an approach at the intersection of neuroscience, cognitive engineering and human factors, which aims to create better human–system interaction. Eye-tracking technology allows users to “monitor the monitoring” by providing insights into both pilots’ attentional distribution and underlying decisional processes. In this position paper, we identify and define a framework of four stages of step-by-step integration of eye-tracking systems in modern cockpits. Stage I concerns Pilot Training and Flight Performance Analysis on-ground; stage II proposes On-board Gaze Recordings as extra data for the “black box” recorders; stage III describes Gaze-Based Flight Deck Adaptation including warning and alerting systems, and, eventually, stage IV prophesies Gaze-Based Aircraft Adaptation including authority taking by the aircraft. We illustrate the potential of these four steps with a description of incidents or accidents that we could certainly have avoided thanks to eye-tracking. Estimated milestones for the integration of each stage are also proposed together with a list of some implementation limitations. We believe that the research institutions and industrial actors of the domain will all benefit from the integration of the framework of the eye-tracking systems into cockpits.

  5. Comparing the cardiovascular therapeutic indices of glycopyrronium and tiotropium in an integrated rat pharmacokinetic, pharmacodynamic and safety model

    Energy Technology Data Exchange (ETDEWEB)

    Trifilieff, Alexandre; Ethell, Brian T. [Respiratory Disease Area, Novartis Institutes for Biomedical Research, Wimblehurst Road, Horsham, West Sussex RH12 5AB (United Kingdom); Sykes, David A. [Respiratory Disease Area, Novartis Institutes for Biomedical Research, Wimblehurst Road, Horsham, West Sussex RH12 5AB (United Kingdom); School of Life Sciences, Queen' s Medical Centre, University of Nottingham, Nottingham, NG7 2UH (United Kingdom); Watson, Kenny J.; Collingwood, Steve [Respiratory Disease Area, Novartis Institutes for Biomedical Research, Wimblehurst Road, Horsham, West Sussex RH12 5AB (United Kingdom); Charlton, Steven J. [Respiratory Disease Area, Novartis Institutes for Biomedical Research, Wimblehurst Road, Horsham, West Sussex RH12 5AB (United Kingdom); School of Life Sciences, Queen' s Medical Centre, University of Nottingham, Nottingham, NG7 2UH (United Kingdom); Kent, Toby C., E-mail: tobykent@me.com [Respiratory Disease Area, Novartis Institutes for Biomedical Research, Wimblehurst Road, Horsham, West Sussex RH12 5AB (United Kingdom)

    2015-08-15

    Long acting inhaled muscarinic receptor antagonists, such as tiotropium, are widely used as bronchodilator therapy for chronic obstructive pulmonary disease (COPD). Although this class of compounds is generally considered to be safe and well tolerated in COPD patients the cardiovascular safety of tiotropium has recently been questioned. We describe a rat in vivo model that allows the concurrent assessment of muscarinic antagonist potency, bronchodilator efficacy and a potential for side effects, and we use this model to compare tiotropium with NVA237 (glycopyrronium bromide), a recently approved inhaled muscarinic antagonist for COPD. Anaesthetized Brown Norway rats were dosed intratracheally at 1 or 6 h prior to receiving increasing doses of intravenous methacholine. Changes in airway resistance and cardiovascular function were recorded and therapeutic indices were calculated against the ED{sub 50} values for the inhibition of methacholine-induced bronchoconstriction. At both time points studied, greater therapeutic indices for hypotension and bradycardia were observed with glycopyrronium (19.5 and 28.5 fold at 1 h; > 200 fold at 6 h) than with tiotropium (1.5 and 4.2 fold at 1 h; 4.6 and 5.5 fold at 6 h). Pharmacokinetic, protein plasma binding and rat muscarinic receptor binding properties for both compounds were determined and used to generate an integrated model of systemic M{sub 2} muscarinic receptor occupancy, which predicted significantly higher M{sub 2} receptor blockade at ED{sub 50} doses with tiotropium than with glycopyrronium. In our preclinical model there was an improved safety profile for glycopyrronium when compared with tiotropium. - Highlights: • We use an in vivo rat model to study CV safety of inhaled muscarinic antagonists. • We integrate protein and receptor binding and PK of tiotropium and glycopyrrolate. • At ED{sub 50} doses for bronchoprotection we model systemic M{sub 2} receptor occupancy. • Glycopyrrolate demonstrates lower M

  6. Chemical Approach to Biological Safety: Molecular-Level Control of an Integrated Zinc Finger Nuclease

    DEFF Research Database (Denmark)

    Németh, Eszter; Asaka, Masamitsu N; Kato, Kohsuke

    2018-01-01

    circular dichroism spectroscopy, and nano-electrospray ionisation mass spectrometry. In situ intramolecular activation of the nuclease domain was observed, resulting in specific cleavage of DNA with moderate activity. This study represents a new approach to AN design through integrated nucleases consisting......Application of artificial nucleases (ANs) in genome editing is still hindered by their cytotoxicity related to off-target cleavages. This problem can be targeted by regulation of the nuclease domain. Here, we provide an experimental survey of computationally designed integrated zinc finger...... nucleases, constructed by linking the inactivated catalytic centre and the allosteric activator sequence of the colicin E7 nuclease domain to the two opposite termini of a zinc finger array. DNA specificity and metal binding were confirmed by electrophoretic mobility shift assays, synchrotron radiation...

  7. Integrated simulation, evaluation of the climatic risks and safety policies. Synthesis report july 2002

    International Nuclear Information System (INIS)

    Hourcade, J.Ch.; LeTreut, H.

    2002-07-01

    The aim of this program is the improvement of the natural phenomena representation in the integrated models of the climate policies evaluation and to precise the methodological problems resulting from the damages treatment. It underlines the importance of the retroactions between the CO 2 emissions, the lands affectation and the carbon cycle, as the importance of the uncertainties on the climate sensitivity. (A.L.B.)

  8. Experimental study on design verification of new concept for integral reactor safety system

    International Nuclear Information System (INIS)

    Chung, Moon Ki; Choi, Ki Yong; Park, Hyun Sik; Cho, Seok; Park, Choon Kyung; Lee, Sung Jae; Song, Chul Hwa

    2004-01-01

    The pressurized light water cooled, medium power (330 MWt) SMART (System-integrated Modular Advanced ReacTor) has been under development at KAERI for a dual purpose : seawater desalination and electricity generation. The SMART design verification phase was followed to conduct various separate effects tests and comprehensive integral effect tests. The high temperature / high pressure thermal-hydraulic test facility, VISTA(Experimental Verification by Integral Simulation of Transient and Accidents) has been constructed to simulate the SMART-P (the one fifth scaled pilot plant) by KAERI. Experimental tests have been performed to investigate the thermal-hydraulic dynamic characteristics of the primary and the secondary systems. Heat transfer characteristics and natural circulation performance of the PRHRS (Passive Residual Heat Removal System) of SMART-P were also investigated using the VISTA facility. The coolant flows steadily in the natural circulation loop which is composed of the Steam Generator (SG) primary side, the secondary system, and the PRHRS. The heat transfers through the PRHRS heat exchanger and ECT are sufficient enough to enable the natural circulation of the coolant

  9. Development of an administrative system for an integral program of safety and occupational hygiene

    International Nuclear Information System (INIS)

    Dominguez R, J.

    2004-01-01

    The objective of the present investigation thesis will be to provide a clear application of the basic elements of the administration for the elaboration of an integral program of security and occupational hygiene that serves like guide for the creation of new programs and of an internal integral regulation, in the matter. For the above mentioned the present work of thesis investigation besides applying those basic elements of the integral administration will be given execution to the normative one effective as well as the up-to-date concepts of security and hygiene for that the present thesis will be based on these premises that guided us for the elaboration of the program of security and occupational hygiene and that it will serve like base to be applied in all the areas of the National Institute of Nuclear Research and in special in those that are certifying for the system of administration of quality ISO 9001:2000 that with their implantation the objectives were reached that the Institute it has been traced in their general politics. It is necessary to make mention that the Institute has a primordial activity that is the one of to make Research and Development in nuclear matter for the peaceful uses of the nuclear energy, for that that with a strong support of the conventional areas of the type industrial the institutional objectives are achieved, for what is in these areas where the present thesis investigation is developed, without stopping to revise and to apply the nuclear normativity. (Author)

  10. Integrated Safety Assessment (ISA): An approach for the assessment of the software aspects of protection systems

    International Nuclear Information System (INIS)

    Izquierdo-Rocha, Jose Maria; Sanchez-Perea, Miguel; Cojazzi, Giacomo

    2004-01-01

    This paper reviews the main features of ISA, a concept developed as a result of previous work on safety assessment and dynamic reliability. The method links the dynamics of the facility with its operating environment, subject to transitions between different time evolutions due to failures and/or system/operator interventions. For situations dominated by Deterministic Transitions (i.e., transitions upon deterministic demands as a result for instance of exceeding automatic-actions/alarm setpoints), the methodology can be considered an extension of PSA and accident analysis techniques that replaces the static event tree with a Deterministic Dynamic Event Tree (DDET) concept based on the Theory of Probabilistic Dynamics. The paper also summarizes some results of an ISA application to the assessment of the Emergency Operating Procedure (EOP) of a PWR-W to mitigate the Steam Generator Tube Rupture (SGTR) initiating event. (author)

  11. Technology Development for Integrated Safety Test of Spent Nuclear Fuel Transportation and Storage System

    International Nuclear Information System (INIS)

    Seo, Kiseog; Seo, J. S.; Lee, J. C.

    2012-05-01

    A dedicated review on the U. S. NRC Regulation 10 CFR Part 72 and regulatory guide NUREG/1536 has been performed. The safety requirements for spent nuclear fuel dry storage cask are analyzed and summarized in structural, thermal, shielding, criticality, materials, tests and maintenance aspects. Also a guideline for preparing the safety analysis report is provided. The heat flow analysis was performed by varying the dimensions of the heat flow test facility. From the heat flow analysis for the test facility, as the test facility became test facility. From the heat flow analysis for the test facility, as the test facility became bigger; the thermal effect became smaller. Therefore, the dimensions of the heat flow test facility was designed with 5m Χ 5m Χ 6m(H). Analyses of heat transfer characteristics and mechanism for spent PWR fuel assemblies, option study for production of the effective thermal conductivity and option study for effective thermal conductivity test have been performed to obtain the basic data for production of the effective thermal conductivity. It became clear that the diffusion coefficient of chloride ion of concrete remarkably increases along with the temperature rise, and that there is a linear relation between the logarithm values of the diffusion coefficients and the reciprocal of the temperature. It is understood to be able to express the temperature dependency of the diffusion coefficient roughly by an Arrhenius equation as the velocity coefficient is provided as the diffusion coefficient. The specifications and characteristics of storage facilities under operation including dual purpose casks were investigated. Components subject to material degradation were examined. Based on literature survey, investigating a drop analysis incorporating with material degradation, the basic data to develop an analysis methodology was obtained

  12. Integrating gender medicine into the workplace health and safety policy in the scientific research institutions: a mandatory task.

    Science.gov (United States)

    Giammarioli, Anna Maria; Siracusano, Alessandra; Sorrentino, Eugenio; Bettoni, Monica; Malorni, Walter

    2012-01-01

    Gender medicine is a multi-faceted field of investigation integrating various aspects of psycho-social and biological sciences but it mainly deals with the impact of the gender on human physiology, pathophysiology, and clinical features of diseases. In Italy, the Decree Law 81/2008 recently introduced the gender issue in the risk assessment at the workplaces. This review briefly describes our current knowledge on gender medicine and on the Italian legislation in risk management. Public or private scientific institutions should be the first to pay attention to the safety of their workers, who are simultaneously subjected to biological, chemical and physical agents. Main tasks of risk management in scientific research institutions are here analyzed and discussed in a gender perspective.

  13. Integrating gender medicine into the workplace health and safety policy in the scientific research institutions: a mandatory task

    Directory of Open Access Journals (Sweden)

    Anna Maria Giammarioli

    2012-01-01

    Full Text Available BACKGROUND: Gender medicine is a multi-faceted field of investigation integrating various aspects of psycho-social and biological sciences but it mainly deals with the impact of the gender on human physiology, pathophysiology, and clinical features of diseases. In Italy, the Decree Law 81/2008 recently introduced the gender issue in the risk assessment at the workplaces. AIMS: This review briefly describes our current knowledge on gender medicine and on the Italian legislation in risk management. CONCLUSIONS: Public or private scientific institutions should be the first to pay attention to the safety of their workers, who are simultaneously subjected to biological, chemical and physical agents. Main tasks of risk management in scientific research institutions are here analyzed and discussed in a gender perspective.

  14. The World Health Organization's water safety plan is much more than just an integrated drinking water quality management plan.

    Science.gov (United States)

    Viljoen, F C

    2010-01-01

    South Africa is a country of contrasts with far ranging variations in climate, precipitation rates, cultures, demographics, housing levels, education, wealth and skills levels. These differences have an impact on water services delivery as do expectations, affordability and available resources. Although South Africa has made much progress in supplying drinking water, the same cannot be said regarding water quality throughout the country. A concerted effort is currently underway to correct this situation and as part of this drive, water safety plans (WSP) are promoted. Rand Water, the largest water services provider in South Africa, used the World Health Organization (WHO) WSP framework as a guide for the development of its own WSP which was implemented in 2003. Through the process of implementation, Rand Water found the WHO WSP to be much more than just another integrated quality system.

  15. Conceptual design of an integrated information system for safety related analysis of nuclear power plants (IRIS Phase 1)

    International Nuclear Information System (INIS)

    Hofer, K.; Zehnder, P.; Galperin, A.

    1994-01-01

    This report deals with a conceptual design of an integrated information management system, called PSI-IRIS, as needed to assist the analysts for reactor safety related investigations on Swiss nuclear power plants within the project STARS. Performing complicated engineering analyses of an NPP requires storage and manipulation of a large amount of information, both data and knowledge. This information is characterized by its multi-disciplinary nature, complexity, and diversity. The problems caused by inefficient and lengthy manual operations involving the data flow management within the framework of the safety related analysis of an NPP, can be solved by applying computer aided engineering (CAE) principles. These principles are the basis for the design of the integrated information management system PSI-IRIS presented in this report. The basic idea is to create a computerized environment, which includes both database and functional capabilities. The database of the PSI-IRIS consists of two parts, an NPP generic database (GDB) and a collection of analysis results (CASE L IB). The GDB includes all technical plant data and information needed to generate input decks for all computer codes utilized within the STARS project. The CASE L IB storage contains the accumulated knowledge, input decks, and result files of the NPP transient analyses. Considerations and analysis of the data types and the required data manipulation capabilities as well as operational requirements resulted in the choice of an object-oriented database management system (OODBMS) as a development platform for solving the software engineering problems. Several advantages of OODBMS's over conventional relational database management systems were found of crucial importance, especially providing the necessary flexibility for different data types and the potential for extensibility. (author) 15 figs., tabs., 20 refs

  16. Proposal of a risk-factor-based analytical approach for integrating occupational health and safety into project risk evaluation.

    Science.gov (United States)

    Badri, Adel; Nadeau, Sylvie; Gbodossou, André

    2012-09-01

    Excluding occupational health and safety (OHS) from project management is no longer acceptable. Numerous industrial accidents have exposed the ineffectiveness of conventional risk evaluation methods as well as negligence of risk factors having major impact on the health and safety of workers and nearby residents. Lack of reliable and complete evaluations from the beginning of a project generates bad decisions that could end up threatening the very existence of an organization. This article supports a systematic approach to the evaluation of OHS risks and proposes a new procedure based on the number of risk factors identified and their relative significance. A new concept called risk factor concentration along with weighting of risk factor categories as contributors to undesirable events are used in the analytical hierarchy process multi-criteria comparison model with Expert Choice(©) software. A case study is used to illustrate the various steps of the risk evaluation approach and the quick and simple integration of OHS at an early stage of a project. The approach allows continual reassessment of criteria over the course of the project or when new data are acquired. It was thus possible to differentiate the OHS risks from the risk of drop in quality in the case of the factory expansion project. Copyright © 2011 Elsevier Ltd. All rights reserved.

  17. Point-Cloud Compression for Vehicle-Based Mobile Mapping Systems Using Portable Network Graphics

    Science.gov (United States)

    Kohira, K.; Masuda, H.

    2017-09-01

    A mobile mapping system is effective for capturing dense point-clouds of roads and roadside objects Point-clouds of urban areas, residential areas, and arterial roads are useful for maintenance of infrastructure, map creation, and automatic driving. However, the data size of point-clouds measured in large areas is enormously large. A large storage capacity is required to store such point-clouds, and heavy loads will be taken on network if point-clouds are transferred through the network. Therefore, it is desirable to reduce data sizes of point-clouds without deterioration of quality. In this research, we propose a novel point-cloud compression method for vehicle-based mobile mapping systems. In our compression method, point-clouds are mapped onto 2D pixels using GPS time and the parameters of the laser scanner. Then, the images are encoded in the Portable Networking Graphics (PNG) format and compressed using the PNG algorithm. In our experiments, our method could efficiently compress point-clouds without deteriorating the quality.

  18. POINT-CLOUD COMPRESSION FOR VEHICLE-BASED MOBILE MAPPING SYSTEMS USING PORTABLE NETWORK GRAPHICS

    Directory of Open Access Journals (Sweden)

    K. Kohira

    2017-09-01

    Full Text Available A mobile mapping system is effective for capturing dense point-clouds of roads and roadside objects.Point-clouds of urban areas, residential areas, and arterial roads are useful for maintenance of infrastructure, map creation, and automatic driving. However, the data size of point-clouds measured in large areas is enormously large. A large storage capacity is required to store such point-clouds, and heavy loads will be taken on network if point-clouds are transferred through the network. Therefore, it is desirable to reduce data sizes of point-clouds without deterioration of quality. In this research, we propose a novel point-cloud compression method for vehicle-based mobile mapping systems. In our compression method, point-clouds are mapped onto 2D pixels using GPS time and the parameters of the laser scanner. Then, the images are encoded in the Portable Networking Graphics (PNG format and compressed using the PNG algorithm. In our experiments, our method could efficiently compress point-clouds without deteriorating the quality.

  19. Management of Innovative Projects for Ensuring the Economic Safety in the Conditions of Integration of Economies into the World Economy

    Directory of Open Access Journals (Sweden)

    T. K. Usmanova

    2017-01-01

    Full Text Available Purpose: the aim of the article is to reveal problems and prospects, formulate economic security within the framework of innovation projects management, plan technologies in the context of integrating economies into the world economy, identify opportunities for forming, organizing, financing, managing priority economic directions. The subject is the management of innovative projects to ensure the economic security of Russian regions. The relevance of the chosen topic is due to the study of the features of the current state and the problems of the formation of economic security, the development of innovative design solutions in the context of integrating economies into the world economy. Ensuring the economic security of the regions of Russia directly depends on the introduction of innovative technologies and project management in the sectors of the national economy of Russia. Methods: the methodology of the solution of objectives is based on usage of a method of dialectic research, methods of the economic analysis, forecasting, the situational and systemic analysis, expert evaluations and the analysis of empirical data. Hypothesis. Ensuring an economic safety requires formation of innovative solutions, change of the current legislation within the Strategy of social and economic development in the conditions of integration of economies into the world economy. Results: the practical significance of the work is to identify the interrelationship between the development processes of innovative projects that ensure the economic security of the regions of Russia within the framework of regulating the current legislation, forecasting effective economic activity within the framework of the New Industrialization Strategy, selecting optimal project planning models to ensure the country's economic security and competitiveness in the conditions of integration Economies into the world economy. Conclusions and Relevance: in the conditions of integration of

  20. Integrated safety assessment of Indian nuclear power plants for extreme events: reducing impact on public mind

    International Nuclear Information System (INIS)

    Kakodkar, Anil; Singh, Ram Kumar

    2013-01-01

    Nuclear energy professionals need to understand and address the catastrophe syndrome that of late seems to be increasingly at work in public mind in the context of nuclear energy. Classically the nuclear power reactor design and system evolution has been based on the logic of minimization of risk to an acceptable level and its quantification based on a deterministic approach and backed up by a further assessment based on the probabilistic methodology. However, in spite of minimization of risk, the reasons for anxiety and trauma in public mind that still prevails in the context of severe accidents needs to be understood and addressed. Margins between maximum credible accidents factored in the design and the ultimate load withstanding capacities of relevant systems need to be enhanced and guaranteed with a view to minimize release of radioactivity and avoid serious impact in public domain. A more realistic basis for management of an accident in public domain also needs to be quantified for this purpose. Assurance to public on limiting the consequences to a level that does not lead to a trauma is something that we need to be able to credibly demonstrate and confirm. The findings from Chernobyl reports point to significant psychological effects and related health disorders due to large scale emergency relocation of people that could have been possibly reduced by an order of magnitude without significant additional safety detriment

  1. Realistic integration of sorption processes in transport codes for long-term safety assessments

    Energy Technology Data Exchange (ETDEWEB)

    Noseck, Ulrich; Fluegge, Judith; Britz, Susan; Schneider, Anke [Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH (GRS), Koeln (Germany); Brendler, Vinzenz; Stockmann, Madlen; Schikora, Johannes [Helmholtz-Zentrum Dresden-Rossendorf e.V., Dresden (Germany); Lampe, Michael [Frankfurt Univ. (Germany). Goethe Center for Scientific Computing

    2012-09-15

    One important aspect in long-term safety assessment is related to radionuclide transport in geologic formations. In order to assess its consequences over assessment periods of one million years numerical models describing flow and transport are applied. Sorption on mineral surfaces is the most relevant process retarding radionuclide transport. On the one hand an increased transport time might cause a decrease in radionuclide concentration by radioactive decay. On the other hand it might increase concentrations of dose-relevant daughter nuclides in decay chains. In order to treat the radionuclide sorption processes in natural systems close to reality the so-called smart K{sub d}-concept is implemented into the transport program r{sup 3}t, which is applied to large model areas and very long time scales in long-term safety assessment. In the first stage this approach is developed for a typical sedimentary system covering rock salt and clay formations in Northern Germany. The smart K{sub d}-values are based on mechanistic surface complexation models (SCM), varying in time and space and de-pending on the actual geochemical conditions, which might change in the future e. g. due to the impact of climate changes. The concept developed and introduced here is based on a feasible treatment of the most relevant geochemical parameters in the transport code as well as on a matrix of smart K{sub d}-values calculated in dependence on these parameters. The implementation of the concept comprises the selection of relevant elements and minerals to be considered, an experimental program to fill data gaps of the thermody-namic sorption database, an uncertainty and sensitivity analysis to identify the most important environmental parameters influencing sorption of long-term relevant radionu-clides, the creation of a matrix with K{sub d}-values dependent on the selected environmental parameters, and the development and realisation of the conceptual model for treatment of temporal and

  2. Exploratory Nuclear Reactor Safety Analysis and Visualization via Integrated Topological and Geometric Techniques

    Energy Technology Data Exchange (ETDEWEB)

    Maljovec, Dan [Univ. of Utah, Salt Lake City, UT (United States); Wang, Bei [Univ. of Utah, Salt Lake City, UT (United States); Pascucci, Valerio [Univ. of Utah, Salt Lake City, UT (United States); Bremer, Peer-Timo [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Mandelli, Diego [Idaho National Lab. (INL), Idaho Falls, ID (United States); Pernice, Michael [Idaho National Lab. (INL), Idaho Falls, ID (United States); Nourgaliev, Robert [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2013-10-01

    A recent trend in the nuclear power engineering field is the implementation of heavily computational and time consuming algorithms and codes for both design and safety analysis. In particular, the new generation of system analysis codes aim to embrace several phenomena such as thermo-hydraulic, structural behavior, and system dynamics, as well as uncertainty quantification and sensitivity analyses. The use of dynamic probabilistic risk assessment (PRA) methodologies allows a systematic approach to uncertainty quantification. Dynamic methodologies in PRA account for possible coupling between triggered or stochastic events through explicit consideration of the time element in system evolution, often through the use of dynamic system models (simulators). They are usually needed when the system has more than one failure mode, control loops, and/or hardware/process/software/human interaction. Dynamic methodologies are also capable of modeling the consequences of epistemic and aleatory uncertainties. The Monte-Carlo (MC) and the Dynamic Event Tree (DET) approaches belong to this new class of dynamic PRA methodologies. The major challenges in using MC and DET methodologies (as well as other dynamic methodologies) are the heavier computational and memory requirements compared to the classical ET analysis. This is due to the fact that each branch generated can contain time evolutions of a large number of variables (about 50,000 data channels are typically present in RELAP) and a large number of scenarios can be generated from a single initiating event (possibly on the order of hundreds or even thousands). Such large amounts of information are usually very difficult to organize in order to identify the main trends in scenario evolutions and the main risk contributors for each initiating event. This report aims to improve Dynamic PRA methodologies by tackling the two challenges mentioned above using: 1) adaptive sampling techniques to reduce computational cost of the analysis

  3. Integrated approach to fire safety at the Krsko nuclear power plant - fire protection action plan

    International Nuclear Information System (INIS)

    Lambright, J.A.; Cerjak, J.; Spiler, J.; Ioannidi, J.

    1998-01-01

    Nuclear Power Plant Krsko (NPP Krsko) is a Westinghouse design, single-unit, 1882 Megawatt thermal (MWt), two-loop, pressurized water nuclear power plant. The fire protection program at NPP Krsko has been reviewed and reports issued recommending changes and modifications to the program, plant systems and structures. Three reports were issued, the NPP Krsko Fire Hazard Analysis (Safe Shout down Separation Analysis Report), the ICISA Analysis of Core Damage Frequency Due to Fire at the NPP Krsko and IPEEE (Individual Plant External Event Examination) related to fire risk. The Fire Hazard Analysis Report utilizes a compliance - based deterministic approach to identification of fire area hazards. This report focuses on strict compliance from the perspective of US Nuclear Regulatory Commission (USNRC), standards, guidelines and acceptance criteria and does not consider variations to comply with the intent of the regulations. The probabilistic analysis methide used in the ICISA and IPEEE report utilizes a risk based nad intent based approach in determining critical at-risk fire areas. NPP Krsko has already completed the following suggestions/recommendations from the above and OSART reports in order to comply with Appendix R: Installation of smoke detectors in the Control Room; Installation of Emergency Lighting in some plant areas and of Remote Shout down panels; Extension of Sound Power Communication System; Installation of Fire Annunciator Panel at the On-site Fire Brigade Station; Installation of Smoke Detection System in the (a) Main Control Room Panels, (b) Essential Service Water Building. (c) Component Cooling Building pump area, chiller area and HVAC area, (d) Auxiliary Building Safety pump rooms, (e) Fuel Handling room, (f) Intermediate Building AFFW area and compressor room, and (g) Tadwaste building; inclusion of Auxiliary operators in the Fire Brigade; training of Fire Brigade Members in Plant Operation (9 week course); Development of Fire Door Inspection and

  4. Application of Integrated Verification Approach to FPGA-based Safety-Critical I and C System of Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Ahmed, Ibrahim; Heo, Gyunyoung [Kyunghee Univ., Yongin (Korea, Republic of); Jung, Jaecheon [KEPCO, Ulsan (Korea, Republic of)

    2016-10-15

    Safety-critical instrumentation and control (I and C) system in nuclear power plant (NPP) implemented on programmable logic controllers (PLCs) plays a vital role in safe operation of the plant. The challenges such as fast obsolescence, the vulnerability to cyber-attack, and other related issues of software systems have currently led to the consideration of field programmable gate arrays (FPGAs) as an alternative to PLCs because of their advantages and hardware related benefits. Generally in FPGA design verification, the designers make use of verification techniques by writing the test benches which involved various stages of verification activities of register-transfer level (RTL), gate-level, and place and route. Writing the test benches is considerably time consuming and require a lot of efforts to achieve a satisfied desire results. Furthermore, performing the verification at each stage is a major bottleneck and demanded much activities and time. In addition, verification is conceivably, the most difficult and complicated aspect of any design. Therefore, in view of these, this work applied an integrated verification approach to the verification of FPGA-based I and C system in NPP that simultaneously verified the whole design modules using MATLAB/Simulink HDL Co-simulation models. Verification is conceivably, the most difficult and complicated aspect of any design, and an FPGA design is not an exception. Therefore, in this work, we introduced and discussed how an application of integrated verification technique to the verification and testing of FPGA-based I and C system design in NPP can facilitate the verification processes, and verify the entire design modules of the system simultaneously using MATLAB/Simulink HDL co-simulation models. In conclusion, the results showed that, the integrated verification approach through MATLAB/Simulink models, if applied to any design to be verified, could speed up the design verification and reduce the V and V tasks.

  5. Application of Integrated Verification Approach to FPGA-based Safety-Critical I and C System of Nuclear Power Plant

    International Nuclear Information System (INIS)

    Ahmed, Ibrahim; Heo, Gyunyoung; Jung, Jaecheon

    2016-01-01

    Safety-critical instrumentation and control (I and C) system in nuclear power plant (NPP) implemented on programmable logic controllers (PLCs) plays a vital role in safe operation of the plant. The challenges such as fast obsolescence, the vulnerability to cyber-attack, and other related issues of software systems have currently led to the consideration of field programmable gate arrays (FPGAs) as an alternative to PLCs because of their advantages and hardware related benefits. Generally in FPGA design verification, the designers make use of verification techniques by writing the test benches which involved various stages of verification activities of register-transfer level (RTL), gate-level, and place and route. Writing the test benches is considerably time consuming and require a lot of efforts to achieve a satisfied desire results. Furthermore, performing the verification at each stage is a major bottleneck and demanded much activities and time. In addition, verification is conceivably, the most difficult and complicated aspect of any design. Therefore, in view of these, this work applied an integrated verification approach to the verification of FPGA-based I and C system in NPP that simultaneously verified the whole design modules using MATLAB/Simulink HDL Co-simulation models. Verification is conceivably, the most difficult and complicated aspect of any design, and an FPGA design is not an exception. Therefore, in this work, we introduced and discussed how an application of integrated verification technique to the verification and testing of FPGA-based I and C system design in NPP can facilitate the verification processes, and verify the entire design modules of the system simultaneously using MATLAB/Simulink HDL co-simulation models. In conclusion, the results showed that, the integrated verification approach through MATLAB/Simulink models, if applied to any design to be verified, could speed up the design verification and reduce the V and V tasks

  6. Integration of Body Sensor Networks and Vehicular Ad-hoc Networks for Traffic Safety

    Directory of Open Access Journals (Sweden)

    Angelica Reyes-Muñoz

    2016-01-01

    Full Text Available The emergence of Body Sensor Networks (BSNs constitutes a new and fast growing trend for the development of daily routine applications. However, in the case of heterogeneous BSNs integration with Vehicular ad hoc Networks (VANETs a large number of difficulties remain, that must be solved, especially when talking about the detection of human state factors that impair the driving of motor vehicles. The main contributions of this investigation are principally three: (1 an exhaustive review of the current mechanisms to detect four basic physiological behavior states (drowsy, drunk, driving under emotional state disorders and distracted driving that may cause traffic accidents is presented; (2 A middleware architecture is proposed. This architecture can communicate with the car dashboard, emergency services, vehicles belonging to the VANET and road or street facilities. This architecture seeks on the one hand to improve the car driving experience of the driver and on the other hand to extend security mechanisms for the surrounding individuals; and (3 as a proof of concept, an Android real-time attention low level detection application that runs in a next-generation smartphone is developed. The application features mechanisms that allow one to measure the degree of attention of a driver on the base of her/his EEG signals, establish wireless communication links via various standard wireless means, GPRS, Bluetooth and WiFi and issue alarms of critical low driver attention levels.

  7. An integrated approach for Limpopo Park groundwater characterization for biodiversity safety

    Directory of Open Access Journals (Sweden)

    Stefania Vitale

    2016-12-01

    Full Text Available This paper presents a multistep study held in the context of the SECOSUD Phase II project, called “Conservation and equitable use of biological diversity in the SADC region (Southern African Development Community [1]. The present study is developed in the activity research of the SECOSUD Phase II project funded by the Italian Ministry of Foreign Affairs in the SADC. One of this project’s objectives is to strengthen the capacities of the SADC region scientific network, in the aim to consolidate and to harmonize the management of natural resources [1]. The overall objective of this study is to design an integrated approach for Limpopo Park groundwater characterization and management, based on dealing with the full water cycle by a tiered and complex program, which will follow several steps: a preliminary field study, data existing collection, the selection of sites meteorological stations, the location of monitoring surface water and groundwater points, which includes fields measurements and sampling, chemical and isotopic analysis, collection of hydrological data to design hydrological conceptual model in the area under study in order to quantify the water balance and to provide recommendations on where to focus future research. The monitoring systems should be supported by processing procedures, step by step, implementing a GIS database.

  8. Integration of Body Sensor Networks and Vehicular Ad-hoc Networks for Traffic Safety.

    Science.gov (United States)

    Reyes-Muñoz, Angelica; Domingo, Mari Carmen; López-Trinidad, Marco Antonio; Delgado, José Luis

    2016-01-15

    The emergence of Body Sensor Networks (BSNs) constitutes a new and fast growing trend for the development of daily routine applications. However, in the case of heterogeneous BSNs integration with Vehicular ad hoc Networks (VANETs) a large number of difficulties remain, that must be solved, especially when talking about the detection of human state factors that impair the driving of motor vehicles. The main contributions of this investigation are principally three: (1) an exhaustive review of the current mechanisms to detect four basic physiological behavior states (drowsy, drunk, driving under emotional state disorders and distracted driving) that may cause traffic accidents is presented; (2) A middleware architecture is proposed. This architecture can communicate with the car dashboard, emergency services, vehicles belonging to the VANET and road or street facilities. This architecture seeks on the one hand to improve the car driving experience of the driver and on the other hand to extend security mechanisms for the surrounding individuals; and (3) as a proof of concept, an Android real-time attention low level detection application that runs in a next-generation smartphone is developed. The application features mechanisms that allow one to measure the degree of attention of a driver on the base of her/his EEG signals, establish wireless communication links via various standard wireless means, GPRS, Bluetooth and WiFi and issue alarms of critical low driver attention levels.

  9. Safety and resiliency in action: Integrating risk management into local development

    Directory of Open Access Journals (Sweden)

    Ebay Jorge S.

    2013-01-01

    Full Text Available This paper examines the efforts of the local government unit (LGU of San Jose de Buenavista, in the Province of Antique in central Philippines to manage risks associated with multiple hazards to protect the people, their livelihoods and local development gains. More specifically, it analyzes the process of pursuing risk management objectives vis-a-vis national and international disaster risk reduction and management (DRRM norms, without loosing sight of local contextual realities that directly influence people’s vulnerabilities and capacities. Risk management initiatives in the LGU revolve around four key areas namely disaster prevention and mitigation, disaster preparedness, emergency response, and recovery and rehabilitation. Binding these initiatives are actions that integrate governance mechanisms with scientific data and sectoral and community participation to develop a comprehensive plan of action and standard operating procedures that will serve as guideposts in the process of building a safer community. The experience of San Jose de Buenavista also suggests that cost saving strategies an be replicated by communities and organizations that have financial limitations to pursue DRRM objectives. This paper contends that risk management is a fundamental development strategy to pursue local development goals and to sustain efforts to protect development gains in the long run. This can be done using a combination of governance, risk assessment, knowledge management, vulnerability reduction and preparedness strategies. Local leadership, people’s participation, environmental resource management and continuous capability building are key elements of the process. Ultimately, risk management must be mainstreamed into local development to develop community resiliency.

  10. Integration of Body Sensor Networks and Vehicular Ad-hoc Networks for Traffic Safety

    Science.gov (United States)

    Reyes-Muñoz, Angelica; Domingo, Mari Carmen; López-Trinidad, Marco Antonio; Delgado, José Luis

    2016-01-01

    The emergence of Body Sensor Networks (BSNs) constitutes a new and fast growing trend for the development of daily routine applications. However, in the case of heterogeneous BSNs integration with Vehicular ad hoc Networks (VANETs) a large number of difficulties remain, that must be solved, especially when talking about the detection of human state factors that impair the driving of motor vehicles. The main contributions of this investigation are principally three: (1) an exhaustive review of the current mechanisms to detect four basic physiological behavior states (drowsy, drunk, driving under emotional state disorders and distracted driving) that may cause traffic accidents is presented; (2) A middleware architecture is proposed. This architecture can communicate with the car dashboard, emergency services, vehicles belonging to the VANET and road or street facilities. This architecture seeks on the one hand to improve the car driving experience of the driver and on the other hand to extend security mechanisms for the surrounding individuals; and (3) as a proof of concept, an Android real-time attention low level detection application that runs in a next-generation smartphone is developed. The application features mechanisms that allow one to measure the degree of attention of a driver on the base of her/his EEG signals, establish wireless communication links via various standard wireless means, GPRS, Bluetooth and WiFi and issue alarms of critical low driver attention levels. PMID:26784204

  11. Hanford tank initiative vehicle/based waste retrieval demonstration report phase II, track 2

    International Nuclear Information System (INIS)

    Berglin, E.J.

    1997-01-01

    Using the versatile TracPUMpTm, Environmental Specialties Group, LLC (ES) performed a successful Phase 11 demonstration of a Vehicle- Based Waste Retrieval System (VWRS) for removal of waste material and residual liquid found in the Hanford Underground Storage Tanks (ousts). The purpose of this demonstration was to address issues pertaining to the use of a VWRS in OUSTS. The demonstration also revealed the waste removal capabilities of the TracPumpTm and the most effective techniques and equipment to safely and effectively remove waste simulants. ES successfully addressed the following primary issues: I . Dislodge and convey the waste forms present in the Hanford OUSTS; 2. Access the UST through tank openings as small as twenty-four inches in diameter; 3. Traverse a variety of terrains including slopes, sludges, rocks and hard, slippery surfaces without becoming mired; 4. Dislodge and convey waste within the confinement of the Decontamination Containment Capture Vessel (DCCV) and with minimal personnel exposure; 5. Decontaminate equipment to acceptable limits during retrieval from the UST; 6. Perform any required maintenance within the confinement of the DCCV; and 7. Maintain contaminate levels ''as low as reasonably achievable'' (ALARA) within the DCCV due to its crevice and comer-free design. The following materials were used to simulate the physical characteristics of wastes found in Hanford's OUSTS: (1) Hardpan: a clay-type material that has high shear strength; (2) Saltcake: a fertilizer-based material that has high compressive strength; and (3) Wet Sludge.- a sticky, peanut- butter- like material with low shear strength. Four test beds were constructed of plywood and filled with a different simulant to a depth of eight to ten inches. Three of the test beds were of homogenous simulant material, while the fourth bed consisted of a mixture of all three simulant types

  12. Status and integration of the gas generation studies performed for the Hydrogen Safety Program

    International Nuclear Information System (INIS)

    Pederson, L.R.; Strachan, D.M.

    1993-02-01

    Waste in Tank 241-SY-101 on the Hanford Site generates and periodically releases hydrogen, nitrous oxide, and nitrogen gases. Studies have been conducted at several laboratories to determine the chemical mechanisms for the gas generation and release. Results from these studies are presented and integrated in an attempt to describe current understanding of the physical properties of the waste and the mechanisms of gas generation and retention. Existing tank data are consistent with the interpretation that gases are uniformly generated in the tank, released continuously from the convecting layer, and stored in the nonconvecting layer. Tank temperature measurements suggest that the waste consists of ''gobs'' of material that reach neutral buoyancy at different times. The activation energy of the rate limiting step of the gas generating process was calculated to be about 7 kJ/mol but measured in the laboratory at 80 to 100 kJ/mol. Based on observed temperature changes in the tank the activation energy is probably not higher than about 20 kJ/mol. Several simulated waste compositions have been devised for use in laboratory studies in the place of actual waste from Tank 241-SY-101. Data from these studies can be used to predict how the actual waste might behave when heated or diluted. Density evaluations do not confirm that heating waste at the bottom of the tank would induce circulation within the waste; however, heating may release gas bubbles by dissolving the solids to which the bubbles adhere. Gas generation studies on simulated wastes indicated that nitrous oxide and hydrogen yields are not particularly coupled. Solubility studies of nitrous oxide, the most soluble of the principal gaseous products, indicate it is unlikely that dissolved gases contribute substantially to the quantity of gas released during periodic events

  13. Integration

    DEFF Research Database (Denmark)

    Emerek, Ruth

    2004-01-01

    Bidraget diskuterer de forskellige intergrationsopfattelse i Danmark - og hvad der kan forstås ved vellykket integration......Bidraget diskuterer de forskellige intergrationsopfattelse i Danmark - og hvad der kan forstås ved vellykket integration...

  14. WWER-1000 steam generator integrity. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1997-07-01

    Programme was initiated by IAEA in 1990 with the aim to assist the countries of Central and Eastern Europe and former Soviet Union in evaluating the safety of their first generation WWER-440/230 nuclear power plants. The main objectives were: to identify major design and operational safety issues; to establish international consensus on priorities for safety improvements; and to provide assistance in the review of the competence and and adequacy of safety improvement programs. The scope was extended in 1992 ro include RBMK, WWER-440/312 and WWER-1000 plants in operation and under construction. Based on the operational experience of more than 90 reactor years of WWER-1000 NPPs having 80 steam generators in operation or under construction the steam generator integrity was recognized as an important issue of high safety concern. The purpose of this report is to integrate available information on the issue of WWER-1000 steam generator integrity with the focus on the steam generator cold collector damage in particular. This information covers the status of stem generators at operating plants, cause analysis of collector cracking, the damage mechanisms involved, operational aspects and corrective measures developed and implemented. Consideration is given to material, design and fabrication related aspects, operational conditions, system solutions, and in-service inspection. Detailed conclusions and recommendations are provided for each of these aspects

  15. Bridging the Gap: A Framework and Strategies for Integrating the Quality and Safety Mission of Teaching Hospitals and Graduate Medical Education.

    Science.gov (United States)

    Tess, Anjala; Vidyarthi, Arpana; Yang, Julius; Myers, Jennifer S

    2015-09-01

    Integrating the quality and safety mission of teaching hospitals and graduate medical education (GME) is a necessary step to provide the next generation of physicians with the knowledge, skills, and attitudes they need to participate in health system improvement. Although many teaching hospital and health system leaders have made substantial efforts to improve the quality of patient care, few have fully included residents and fellows, who deliver a large portion of that care, in their efforts. Despite expectations related to the engagement of these trainees in health care quality improvement and patient safety outlined by the Accreditation Council for Graduate Medical Education in the Clinical Learning Environment Review program, a structure for approaching this integration has not been described.In this article, the authors present a framework that they hope will assist teaching hospitals in integrating residents and fellows into their quality and safety efforts and in fostering a positive clinical learning environment for education and patient care. The authors define the six essential elements of this framework-organizational culture, teaching hospital-GME alignment, infrastructure, curricular resources, faculty development, and interprofessional collaboration. They then describe the organizational characteristics required for each element and offer concrete strategies to achieve integration. This framework is meant to be a starting point for the development of robust national models of infrastructure, alignment, and collaboration between GME and health care quality and safety leaders at teaching hospitals.

  16. Study on safety of a nuclear ship having an integral marine water reactor. Intelligent information database program concerned with thermal-hydraulic characteristics

    International Nuclear Information System (INIS)

    Inasaka, Fujio; Nariai, Hideki; Kobayashi, Michiyuki; Murata, Hiroyuki; Aya, Izuo

    2001-01-01

    As a high economical marine reactor with sufficient safety functions, an integrated type marine water reactor has been considered most promising. At the National Maritime Research Institute, a series of the experimental studies on the thermal-hydraulic characteristics of an integrated/passive-safety type marine water reactor such as the flow boiling of a helical-coil type steam generator, natural circulation of primary water under a ship rolling motion and flashing-condensation oscillation phenomena in pool water has been conducted. This current study aims at making use of the safety analysis or evaluation of a future marine water reactor by developing an intelligent information database program concerned with the thermal-hydraulic characteristics of an integral/passive-safety reactor on the basis of the above-mentioned valuable experimental knowledge. Since the program was created as a Windows application using the Visual Basic, it is available to the public and can be easily installed in the operating system. Main functions of the program are as follows: (1) steady state flow boiling analysis and determination of stability limit for any helical-coil type once-through steam generator design. (2) analysis and comparison with the flow boiling data, (3) reference and graphic display of the experimental data, (4) indication of the knowledge information such as analysis method and results of the study. The program will be useful for the design of not only the future integrated type marine water reactor but also the small sized water reactor. (author)

  17. Behavioral based safety approaches

    International Nuclear Information System (INIS)

    Maria Michael Raj, I.

    2009-01-01

    Approach towards the establishment of positive safety culture at Heavy Water Plant, Tuticorin includes the adoption of several important methodologies focused on human behavior and culminates with achievement of Total Safety Culture where Quality and Productivity are integrated with Safety

  18. Exercise and rehabilitation delivered through exergames in older adults: An integrative review of technologies, safety and efficacy.

    Science.gov (United States)

    Skjæret, Nina; Nawaz, Ather; Morat, Tobias; Schoene, Daniel; Helbostad, Jorunn Lægdheim; Vereijken, Beatrix

    2016-01-01

    There has been a rapid increase in research on the use of virtual reality (VR) and gaming technology as a complementary tool in exercise and rehabilitation in the elderly population. Although a few recent studies have evaluated their efficacy, there is currently no in-depth description and discussion of different game technologies, physical functions targeted, and safety issues related to older adults playing exergames. This integrative review provides an overview of the technologies and games used, progression, safety measurements and associated adverse events, adherence to exergaming, outcome measures used, and their effect on physical function. We undertook systematic searches of SCOPUS and PubMed databases. Key search terms included "game", "exercise", and "aged", and were adapted to each database. To be included, studies had to involve older adults aged 65 years or above, have a pre-post training or intervention design, include ICT-implemented games with weight-bearing exercises, and have outcome measures that included physical activity variables and/or clinical tests of physical function. Sixty studies fulfilled the inclusion criteria. The studies had a broad range of aims and intervention designs and mostly focused on community-dwelling healthy older adults. The majority of the studies used commercially available gaming technologies that targeted a number of different physical functions. Most studies reported that they had used some form of safety measure during intervention. None of the studies reported serious adverse events. However, only 21 studies (35%) reported on whether adverse events occurred. Twenty-four studies reported on adherence, but only seven studies (12%) compared adherence to exergaming with other forms of exercise. Clinical measures of balance were the most frequently used outcome measures. PEDro scores indicated that most studies had several methodological problems, with only 4 studies fulfilling 6 or more criteria out of 10. Several

  19. Financial Control and Safety. An investigation on how financial and safety aspects are integrated in the decision making at the Swedish nuclear power plants; Ekonomistyrning och saekerhet. En utredning om hur ekonomi- och saekerhetsaspekter integreras vid beslutsfattandet vid kaernkraftverken

    Energy Technology Data Exchange (ETDEWEB)

    Vaernild, Ola [OV Konsult i Vaesteraas AB, Vaesteraas (Sweden)

    2005-08-01

    The alleged inter-relationship between economy and nuclear safety has been investigated. Through interviews and review of instructions and other documents, information on how management at Swedish nuclear power plants integrates financial control and safety management has been compiled. Owners of nuclear power plants have well founded expectations on that the plants are profitable and that the operations are rationalized in order to reduce costs. This could allegedly threaten the nuclear safety. However, it is not to be expected that there are any obvious relationships between expenditures and safety. The quality of the safety management has to be judged in terms of how well safety requirements are met irrespective of the associated costs. The owners have imposed clear financial objectives on the nuclear power plants. At the same time they have also established policies for nuclear safety. The nuclear power plants have systems for operations management, which basically comprise separate parts for operations planning and quality management. Financial control and safety management are included in the operations planning and quality management respectively. The quality management impose restrictions to be adhered to in the operations planning. This means that from a formal point of view, the safety management is superior to the operations planning. There are examples of simple as well as advanced approaches to financial management at the nuclear power plants. In all cases the methods used are reasonably well adapted to the needs. Typical for all plants is the focus on long-term aspects. Investments are for example analysed in a plant life-time perspective. With regard to safety, profitability calculations are not required to the same extent for safety related investments as for other investments. A number of factors, which tend to warrant that safety aspects are given the appropriate attention in the decision making, have been identified. Examples of such factors are

  20. Challenge problem and milestones for : Nuclear Energy Advanced Modeling and Simulation (NEAMS) waste Integrated Performance and Safety Codes (IPSC).

    Energy Technology Data Exchange (ETDEWEB)

    Freeze, Geoffrey A.; Wang, Yifeng; Howard, Robert; McNeish, Jerry A.; Schultz, Peter Andrew; Arguello, Jose Guadalupe, Jr.

    2010-09-01

    This report describes the specification of a challenge problem and associated challenge milestones for the Waste Integrated Performance and Safety Codes (IPSC) supporting the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign. The NEAMS challenge problems are designed to demonstrate proof of concept and progress towards IPSC goals. The goal of the Waste IPSC is to develop an integrated suite of modeling and simulation capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive waste storage or disposal system. The Waste IPSC will provide this simulation capability (1) for a range of disposal concepts, waste form types, engineered repository designs, and geologic settings, (2) for a range of time scales and distances, (3) with appropriate consideration of the inherent uncertainties, and (4) in accordance with robust verification, validation, and software quality requirements. To demonstrate proof of concept and progress towards these goals and requirements, a Waste IPSC challenge problem is specified that includes coupled thermal-hydrologic-chemical-mechanical (THCM) processes that describe (1) the degradation of a borosilicate glass waste form and the corresponding mobilization of radionuclides (i.e., the processes that produce the radionuclide source term), (2) the associated near-field physical and chemical environment for waste emplacement within a salt formation, and (3) radionuclide transport in the near field (i.e., through the engineered components - waste form, waste package, and backfill - and the immediately adjacent salt). The initial details of a set of challenge milestones that collectively comprise the full challenge problem are also specified.

  1. Challenge problem and milestones for: Nuclear Energy Advanced Modeling and Simulation (NEAMS) waste Integrated Performance and Safety Codes (IPSC)

    International Nuclear Information System (INIS)

    Freeze, Geoffrey A.; Wang, Yifeng; Howard, Robert; McNeish, Jerry A.; Schultz, Peter Andrew; Arguello, Jose Guadalupe Jr.

    2010-01-01

    This report describes the specification of a challenge problem and associated challenge milestones for the Waste Integrated Performance and Safety Codes (IPSC) supporting the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign. The NEAMS challenge problems are designed to demonstrate proof of concept and progress towards IPSC goals. The goal of the Waste IPSC is to develop an integrated suite of modeling and simulation capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive waste storage or disposal system. The Waste IPSC will provide this simulation capability (1) for a range of disposal concepts, waste form types, engineered repository designs, and geologic settings, (2) for a range of time scales and distances, (3) with appropriate consideration of the inherent uncertainties, and (4) in accordance with robust verification, validation, and software quality requirements. To demonstrate proof of concept and progress towards these goals and requirements, a Waste IPSC challenge problem is specified that includes coupled thermal-hydrologic-chemical-mechanical (THCM) processes that describe (1) the degradation of a borosilicate glass waste form and the corresponding mobilization of radionuclides (i.e., the processes that produce the radionuclide source term), (2) the associated near-field physical and chemical environment for waste emplacement within a salt formation, and (3) radionuclide transport in the near field (i.e., through the engineered components - waste form, waste package, and backfill - and the immediately adjacent salt). The initial details of a set of challenge milestones that collectively comprise the full challenge problem are also specified.

  2. [Integrity].

    Science.gov (United States)

    Gómez Rodríguez, Rafael Ángel

    2014-01-01

    To say that someone possesses integrity is to claim that that person is almost predictable about responses to specific situations, that he or she can prudentially judge and to act correctly. There is a closed interrelationship between integrity and autonomy, and the autonomy rests on the deeper moral claim of all humans to integrity of the person. Integrity has two senses of significance for medical ethic: one sense refers to the integrity of the person in the bodily, psychosocial and intellectual elements; and in the second sense, the integrity is the virtue. Another facet of integrity of the person is la integrity of values we cherish and espouse. The physician must be a person of integrity if the integrity of the patient is to be safeguarded. The autonomy has reduced the violations in the past, but the character and virtues of the physician are the ultimate safeguard of autonomy of patient. A field very important in medicine is the scientific research. It is the character of the investigator that determines the moral quality of research. The problem arises when legitimate self-interests are replaced by selfish, particularly when human subjects are involved. The final safeguard of moral quality of research is the character and conscience of the investigator. Teaching must be relevant in the scientific field, but the most effective way to teach virtue ethics is through the example of the a respected scientist.

  3. An integrated approach to improved toxicity prediction for the safety assessment during preclinical drug development using Hep G2 cells

    International Nuclear Information System (INIS)

    Noor, Fozia; Niklas, Jens; Mueller-Vieira, Ursula; Heinzle, Elmar

    2009-01-01

    Efficient and accurate safety assessment of compounds is extremely important in the preclinical development of drugs especially when hepatotoxicty is in question. Multiparameter and time resolved assays are expected to greatly improve the prediction of toxicity by assessing complex mechanisms of toxicity. An integrated approach is presented in which Hep G2 cells and primary rat hepatocytes are compared in frequently used cytotoxicity assays for parent compound toxicity. The interassay variability was determined. The cytotoxicity assays were also compared with a reliable alternative time resolved respirometric assay. The set of training compounds consisted of well known hepatotoxins; amiodarone, carbamazepine, clozapine, diclofenac, tacrine, troglitazone and verapamil. The sensitivity of both cell systems in each tested assay was determined. Results show that careful selection of assay parameters and inclusion of a kinetic time resolved assay improves prediction for non-metabolism mediated toxicity using Hep G2 cells as indicated by a sensitivity ratio of 1. The drugs with EC 50 values 100 μM or lower were considered toxic. The difference in the sensitivity of the two cell systems to carbamazepine which causes toxicity via reactive metabolites emphasizes the importance of human cell based in-vitro assays. Using the described system, primary rat hepatocytes do not offer advantage over the Hep G2 cells in parent compound toxicity evaluation. Moreover, respiration method is non invasive, highly sensitive and allows following the time course of toxicity. Respiration assay could serve as early indicator of changes that subsequently lead to toxicity.

  4. TWRS Final Safety Analysis Report (FSAR) integrated control decision team (ICDT) meetings January 22 - 31,1997

    International Nuclear Information System (INIS)

    Saladin, V.L.

    1997-01-01

    U.S. Department of Energy (DOE), Richland Operations Office (RL) letter 97-MSD-163 dated January 15, 1997, directed the Project Hanford Management Contractor (Contractor), Fluor Daniel Hanford, inc., to form a joint RL-Contractor Integrated Control Decision Team (ICDT) to evaluate the Tank Waste Remediation System (TWRS) Final Safety Analysis Report (FSAR) accident scenarios that were identified to be above the risk evaluation guidelines (radiological and/or toxicological) defined by the April 8, 1996, letter from J. Kinzer, RL-TWRS (96-MSO-069) to Dr. A. L. Trego, Westinghouse Hanford Company. The ICDT evaluated six postulated accidents from the draft FSAR which had analyzed consequences above the DOE directed risk evaluation guidelines after controls were applied. The accidents were: (1) Organic Solvent Fires; (2) Organic Salt-Nitrate Fire; (3) Spray Leak; (4) Flammable Gas; (5) Steam Intrusion; and (6) Seismic Event. Five of the postulated accidents exceed radiological risk guidelines. Although the postulated steam intrusion accident does not exceed the radiological risk guidelines, it was considered in the ICDT evaluation because its calculated consequences exceed toxicological risk evaluation guidelines. Figure 1 delineates the mitigated and unmitigated risk evaluations performed for the FSAR

  5. Study of the Continuous Improvement Trend for Health, Safety and Environmental Indicators, after Establishment of Integrated Management System (IMS) in a Pharmaceutical Industry in Iran.

    Science.gov (United States)

    Mariouryad, Pegah; Golbabaei, Farideh; Nasiri, Parvin; Mohammadfam, Iraj; Marioryad, Hossein

    2015-10-01

    Nowadays, organizations try to improve their services and consequently adopt management systems and standards which have become key parts in various industries. One of these management systems which have been noticed in the recent years is Integrated Management System that is the combination of quality, health, safety and environment management systems. This study was conducted with the aim of evaluating the improvement trend after establishment of integrated management system for health, safety and environment indicators, in a pharmaceutical industry in Iran. First, during several inspections in different parts of the industry, indicators that should have been noted were listed and then these indicators were organized in 3 domains of health, safety and environment in the form of a questionnaire that followed Likert method of scaling. Also, the weight of each index was resulted from averaging out of 30 managers and the viewpoints of the related experts in the field. Moreover, by checking the documents and evidence of different years (5 contemplation years of this study), the score of each indicator was determined by multiplying the weight and score of the indices and were finally analysed. Over 5 years, scores of health scope indicators, increased from 161.99 to 202.23. Score in the first year after applying the integrated management system establishment was 172.37 in safety part and in the final year increased to 197.57. The changes of environmental scope rates, from the beginning of the program up to the last year increased from 49.24 to 64.27. Integrated management systems help organizations to improve programs to achieve their objectives. Although in this study all trends of health, safety and environmental indicator changes were positive, but at the same time showed to be slow. So, one can suggest that the result of an annual evaluation should be applied in planning future activities for the years ahead.

  6. Twenty-third water reactor safety information meeting. Volume 3, structural and seismic engineering, primary systems integrity, equipment operability and aging, ECCS strainer blockage research and regulatory issues

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1996-03-01

    This three-volume report contains papers presented at the Twenty- Third Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23-25, 1995. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Italy, Japan, Norway, Russia, Sweden, and Switzerland. This document, Volume 3, presents topics in Structural & Seismic Engineering, Primary Systems Integrity, Equipment Operability and Aging, and ECCS Strainer Blockage Research & Regulatory Issues. Individual papers have been cataloged separately.

  7. Twenty-third water reactor safety information meeting. Volume 3, structural and seismic engineering, primary systems integrity, equipment operability and aging, ECCS strainer blockage research and regulatory issues

    International Nuclear Information System (INIS)

    Monteleone, S.

    1996-03-01

    This three-volume report contains papers presented at the Twenty- Third Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23-25, 1995. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Italy, Japan, Norway, Russia, Sweden, and Switzerland. This document, Volume 3, presents topics in Structural ampersand Seismic Engineering, Primary Systems Integrity, Equipment Operability and Aging, and ECCS Strainer Blockage Research ampersand Regulatory Issues. Individual papers have been cataloged separately

  8. Lessons from American-German nuclear power plant construction. Quality, safety and costs of an attempt to integrate American and German nuclear power plant technology

    International Nuclear Information System (INIS)

    Buchwald, K.

    1979-05-01

    The 1300 MW nuclear power plant at Muelheim-Kaerlich has been under construction since the beginning of 1975. It is being equipped with a pressurised water reactor which has been adapted to the German client's requirements and German licensing practice, based on a license held by Babcock and Wilcox USA (B and W). The problems which have arisen in making this adaptation are the result of different requirements in the USA and the Federal Republic of Germany which make it very difficult to integrate the two technologies. Full integration will almost certainly be impossible, but integration to the widest possible extent is important because it might mean both greater safety and reduced costs. In this article it is intended to show where the problems of integration lie and how they might perhaps be overcome. (author)

  9. Nuclear installations: if the biotechnologist is involved sooner in the evaluation of design, safety worries are better integrated

    International Nuclear Information System (INIS)

    Charron, S.; Tosello, M.

    1995-01-01

    The institutional background to the safety assessment of nuclear installations is based upon tripartite links between the operator of a complex and hazardous process, the regulatory authorities and their technical support services. The biotechnologists responsible for the human factor side of the safety assessment are better able to deal with this complex situation if they get involved at the very outset of a project: in order to reach a compromise that is more acceptable from the safety standpoint. (authors). 7 refs

  10. Integrated Plant Safety Assessment: Systematic Evaluation Program. Yankee Nuclear Power Station, Yankee Atomic Electric Company, Docket No. 50-29. Final report

    International Nuclear Information System (INIS)

    1983-06-01

    The Systematic Evaluation program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of Yankee Nuclear Power Station, operated by Yankee Atomic Electric Company. The Yankee plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review

  11. Integrated plant safety assessment. Systematic Evaluation Program. La Crosse Boiling Water Reactor. Dairyland Power Cooperative, Docket No. 50-409. Final report

    International Nuclear Information System (INIS)

    1983-06-01

    The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of the La Crosse Boiling Water Reactor, operated by Dairyland Power Cooperative. The La Crosse plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review

  12. Integrated Plant Safety Assessment, Systematic Evaluation Program. Yankee Nuclear Power Station, Yankee Atomic Electric Company, Docket No. 50-29. Draft report

    International Nuclear Information System (INIS)

    1983-02-01

    The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of Yankee Nuclear Power Station, operated by Yankee Atomic Electric Company. The Yankee plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review

  13. Integrated plant safety assessment: Systematic Evaluation Program. LaCrosse Boiling Water Reactor, Dairyland Power Cooperative, Docket No. 50-409

    International Nuclear Information System (INIS)

    1983-04-01

    The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of the La Crosse Boiling Water Reactor, operated by Dairyland Power Cooperative. The La Crosse plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addresed. Equipment and procedural changes have been identified as a result of the review

  14. Integrated Plant Safety Assessment: Systematic Evaluation Program. Haddam Neck Plant, Connecticut Yankee Atomic Power Company, Docket No. 50-213. Final report

    International Nuclear Information System (INIS)

    1983-01-01

    The Systematic Evaluation Progam was initiated in February 1977 by the US Nuclear Regulatory Commission review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides: (1) an assessment of how these plants compare with curent licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of Haddam Neck Plant, operated by Connecticut Yankee Atomic Power Company. The Haddam Neck Plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review

  15. Design Method of ADAS for Urban Electric Vehicle Based on Virtual Prototyping

    Directory of Open Access Journals (Sweden)

    Katarzyna Jezierska-Krupa

    2018-01-01

    Full Text Available Since 2012, the Smart Power Team has been actively participating in the Shell Eco-marathon, which is a worldwide competition. From the very beginning, the team has been working to increase driver’s safety on the road by developing Advanced Driver Assistance Systems. This paper presents unique method for designing ADAS systems in order to minimize the costs of the design phase and system implementation and, at the same time, to maximize the positive effect the system has on driver and vehicle safety. The described method is based on using virtual prototyping tool to simulate the system performance in real-life situations. This approach enabled an iterative design process, which resulted in reduction of errors with almost no prototyping and testing costs.

  16. Strengths, weaknesses, opportunities, and threats analysis of integrating the World Health Organization patient safety curriculum into undergraduate medical education in Pakistan: a qualitative case study

    Directory of Open Access Journals (Sweden)

    Samreen Misbah

    2017-12-01

    Full Text Available Purpose The purpose of this study was to conduct a strengths, weaknesses, opportunities, and threats (SWOT analysis of integrating the World Health Organization (WHO patient safety curriculum into undergraduate medical education in Pakistan. Methods A qualitative interpretive case study was conducted at Riphah International University, Islamabad, from October 2016 to June 2017. The study included 9 faculty members and 1 expert on patient safety. The interviews were audiotaped, and a thematic analysis of the transcripts was performed using NVivo software. Results Four themes were derived based on the need analysis model. The sub-themes derived from the collected data were arranged under the themes of strengths, weaknesses, opportunities, and threats, in accordance with the principles of SWOT analysis. The strengths identified were the need for a formal patient safety curriculum and its early integration into the undergraduate program. The weaknesses were faculty awareness and participation in development programs. The opportunities were an ongoing effort to develop an appropriate curriculum, to improve the current culture of healthcare, and to use the WHO curricular resource guide. The threats were attitudes towards patient safety in Pakistani culture, resistance to implementation from different levels, and the role of regulatory authorities. Conclusion The theme of patient safety needs to be incorporated early into the formal medical education curriculum, with the main goals of striving to do no harm and seeing mistakes as opportunities to learn. Faculty development activities need to be organized, and faculty members should to be encouraged to participate in them. The lack of a patient safety culture was identified as the primary reason for resistance to this initiative at many levels. The WHO curriculum, amended according to local institutional culture, can be implemented appropriately with support from the corresponding regulatory bodies.

  17. Strengths, weaknesses, opportunities, and threats analysis of integrating the World Health Organization patient safety curriculum into undergraduate medical education in Pakistan: a qualitative case study.

    Science.gov (United States)

    Misbah, Samreen; Mahboob, Usman

    2017-01-01

    The purpose of this study was to conduct a strengths, weaknesses, opportunities, and threats (SWOT) analysis of integrating the World Health Organization (WHO) patient safety curriculum into undergraduate medical education in Pakistan. A qualitative interpretive case study was conducted at Riphah International University, Islamabad, from October 2016 to June 2017. The study included 9 faculty members and 1 expert on patient safety. The interviews were audiotaped, and a thematic analysis of the transcripts was performed using NVivo software. Four themes were derived based on the need analysis model. The sub-themes derived from the collected data were arranged under the themes of strengths, weaknesses, opportunities, and threats, in accordance with the principles of SWOT analysis. The strengths identified were the need for a formal patient safety curriculum and its early integration into the undergraduate program. The weaknesses were faculty awareness and participation in development programs. The opportunities were an ongoing effort to develop an appropriate curriculum, to improve the current culture of healthcare, and to use the WHO curricular resource guide. The threats were attitudes towards patient safety in Pakistani culture, resistance to implementation from different levels, and the role of regulatory authorities. The theme of patient safety needs to be incorporated early into the formal medical education curriculum, with the main goals of striving to do no harm and seeing mistakes as opportunities to learn. Faculty development activities need to be organized, and faculty members should to be encouraged to participate in them. The lack of a patient safety culture was identified as the primary reason for resistance to this initiative at many levels. The WHO curriculum, amended according to local institutional culture, can be implemented appropriately with support from the corresponding regulatory bodies.

  18. Proceedings of the twenty-fourth water reactor safety information meeting. Volume 2: Reactor pressure vessel embrittlement and thermal annealing; Reactor vessel lower head integrity; Evaluation and projection of steam generator tube condition and integrity

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1997-02-01

    This three-volume report contains papers presented at the Twenty-Fourth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 21--23, 1996. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Czech Republic, Finland, France, Japan, Norway, Russia and United Kingdom. This volume is divided into the following sections: reactor pressure vessel embrittlement and thermal annealing; reactor vessel lower head integrity; and evaluation and projection of steam generator tube condition and integrity. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

  19. Proceedings of the twenty-fourth water reactor safety information meeting. Volume 2: Reactor pressure vessel embrittlement and thermal annealing; Reactor vessel lower head integrity; Evaluation and projection of steam generator tube condition and integrity

    International Nuclear Information System (INIS)

    Monteleone, S.

    1997-02-01

    This three-volume report contains papers presented at the Twenty-Fourth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 21--23, 1996. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Czech Republic, Finland, France, Japan, Norway, Russia and United Kingdom. This volume is divided into the following sections: reactor pressure vessel embrittlement and thermal annealing; reactor vessel lower head integrity; and evaluation and projection of steam generator tube condition and integrity. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database

  20. Design and implementation of an integrated safety management system for compressed natural gas stations using ubiquitous sensor network

    International Nuclear Information System (INIS)

    Yang, Jae Mo; Ko, Byung Seok; Park, Chulhwan; Ko, Jae Wook; Yoo, Byungtae; Shin, Dongil

    2014-01-01

    To increase awareness of safety in facilities where hazards may exist, operators, managers, and executive officers on the site should be able to monitor such facilities. However, most compressed natural gas (CNG) service stations in Korea use only local-mode monitoring, with only on-site operators to monitor the facility. To complement this local-mode monitoring, an online safety management system called Ubiquitous-gas safety management system (U-GSMS) was developed. The U-GSMS consists largely of software and hardware. The software consists of systems that can manage safety and operations, while the hardware consists of sensors installed in the gas facility and wireless communication systems using a ubiquitous sensor network (USN) technology that facilitates communication between sensors as well as between sensors and other devices. As these systems are web-based, on-site operators as well as managers and executive officers at the headquarters can more effectively and efficiently perform monitoring and safety management