Governmental, Legal and Regulatory Framework for Safety. General Safety Requirements. Part 1 (French Edition); Cadre gouvernemental, legislatif et reglementaire de la surete. Prescriptions generales de surete. Partie 1

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-11-15

The objective of this publication is to establish requirements in respect of the governmental, legal and regulatory framework for safety. It covers the essential aspects of the framework for establishing a regulatory body and taking other actions necessary to ensure the effective regulatory control of facilities and activities utilized for peaceful purposes. Other responsibilities and functions, such as liaison within the global safety regime and on support services for safety (including radiation protection), emergency preparedness and response, nuclear security, and the State system of accounting for and control of nuclear material, are also covered.

Complementary Safety Assessments for Research Reactors for the French Nuclear Safety Authority

International Nuclear Information System (INIS)

Kassiotis, Christophe; Rigaud, Antoine; Evrard, Lydie

2013-01-01

The 'Autorite de surete nucleaire' (ASN) requested licensees to undertake stress tests, called complementary safety assessments (CSA), of their installations on May 5th 2011, following the accident that occurred in Japan on March 11th 2011. Their mission consisted in providing feedback on the consequences of potential extreme events. In this process, all the French facilities were divided into three categories of decreasing priority, depending on two main factors: on the one hand, their vulnerability to the various phenomena that led to the Fukushima accident, and on the other hand, the amount of radioactive elements that would be dispersed in the event of a failure of the safety functions. On the 79 high-priority facilities, only five of them are research or experimental reactors (including two currently shutdown or in decommissioning) and their operators (the 'Comissariat a l'energie atomique et aux energies alternatives' (CEA) and the 'Institut Laue Langevin') submitted their reports to the ASN on September 15 th 2011. Concerning the lower-priority facilities, including three other facilities (two research reactors operated by the CEA and a facility operated by ITER Organization) the deadline was September 15 th 2012. Finally, the remaining facilities were not asked to submit a report yet, but they will have to do it later, mainly on the occasion of their next periodic safety review. The analyses of the cliff-edge effects, that may occur in extreme situations (exceptional scale event, combination of several disasters...), led to the definition of a hardened safety core concept by the 'Institut de radioprotection et de surete nucleaire' (IRSN). This hardened safety core of structures, equipment and organizational measures must ensure the ultimate protection of the concerned facilities in extreme situations : it is designed to prevent severe accidents (or curb their progression), limit large scale releases for extreme accidents, and enables the operating teams to

Nuclear safety in France in 2001; La surete nucleaire en France en 2001

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

This press dossier summarizes the highlights of nuclear safety in France in 2001: the point-of-view of A.C. Lacoste, director of the French authority of nuclear safety (ASN), the new organisation of the control of nuclear safety and radiation protection, the ASN's policy of transparency, the evolutions of nuclear fuels and the consistency of the fuel cycle, the necessary evolutions of the nuclear crisis management, the harmonizing work of safety approaches carried out by the WENRA association. The following documents are attached in appendixes: the decrees relative to the reformation of the nuclear control in France, the missions of the ASN, the control of nuclear safety and radiation protection in France, the organization of ASN in March 2000, the incidents notified in 2001, the inspections performed in 2001, and the list of the main French nuclear sites. (J.S.)

Evaluation by the Department de Surete Nucleaire of unsolved PWR safety problems

International Nuclear Information System (INIS)

Dupuis, M.C.; Cayol, A.; Fourest, B.

1980-04-01

The deterministic or probabilistic methods of safety analysis and the analysis of accidents used at the design and construction stage have enabled certain safety problems connected with the PWR programme in France to be identified. Some of these problems have already been stressed by the NRC whereas others are specific to the safety approach practised in France. These problems have led to the adoption of special measurements on the reactors already in operation and should be accounted for in the design of future installations. Analysis of running experience and of incidents should be used to check the validity of the steps taken at the design stage and to identify the weak points of the facilities, especially in their piloting and at the man-machine interface [fr

Re-assessment of safety and ageing; Reevaluations de surete et vieillissement

Energy Technology Data Exchange (ETDEWEB)

Boudot, R.; Dallery, D. [Electricite de France (EDF/DPN), Div. Production Nucleaire 93 - Saint-Denis (France); Delmas, J. [Electricite de France (EDF/DIN), 93 - Saint-Denis (France); Balley, J.; Acalet, R. [Electricite de France (EDF-CIPN), 13 - Marseille (France); Bignan, G.; Mergui, C.; Mazoyer, R.; Maegey, M. [CEA Cadarache, 13 - Saint Paul lez Durance (France); Laigneau, P. [AREVA NP, 92 - Paris La Defense (France)

2007-03-15

The first article presents the research program led conjointly by Cea, EDF and Areva to face ageing of nuclear power plants. 3 axis have been defined: 1) the damaging processes in equipment, 2) the damaging processes in concrete structures, and 3) inspection and monitoring techniques. In the context of the preparation of the third decennial safety review of its 900 MWe PWR units, EDF was asked by the Nuclear Authority (ANS) to write up documentation (DAPE) whose purpose is to show that the aging processes are mastered and adequately handled in the unit concerned and that the carrying on of reactor operation for the next 10 years will not degrade its safety standard. The second article presents the specific purposes of the second (VD2) and third (VD3) decennial safety reviews. The last article deals with the renovation work planned on the Masurca research reactor. Masurca installation is dedicated to the setting of neutron experiments necessary for the validation of neutron calculations in fast neutron spectra configurations. The reactor upgrade will concern: -) the power system, -) the instrumentation and control of the reactor, -) the ventilation of the reactor building, -) the seismic reinforcement of an auxiliary building, -) fire protection, and -) radiation monitoring. (A.C.)

Contribution to the communication: European fuel behaviour perspective

International Nuclear Information System (INIS)

Pickmann, D.O.; Marin, J.F.; Weidinger, H.; Junkrans, S.; Bairiot, H.

1981-08-01

The safety and security problems particular to pressurized water reactors are reviewed. These problems are followed up at statutory level by the Service Central de Surete des Installations Nucleaires (Central Department of Nuclear Installation Safety) and at technical level by the Institut de Protection et de Surete Nucleaire (Nuclear Protection and Safety Institute) linked to the CEA. The safety analysis is based on the design standards and the technical specifications of reactor components and nuclear substances. They relate to the behaviour of a reactor under normal or accidental operation. The fuel elements are studied in the reactor and outside it by means of loops and power ramps. This information is embodied in models which describe the behaviour of the various parts of the reactor during the accident [fr

The safety of radioactive materials transport; La surete des transports de matieres radioactives

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

The rule of the radioactive materials transport contains two different objectives: the safety, or physical protection, consists in preventing the losses, the disappearances, the thefts and the diversions of the nuclear materials (useful materials for weapons); the high civil servant of defence near the Minister of Economy, Finance and Industry is the responsible authority; the safety consists in mastering the risks of irradiation, contamination and criticality presented by the radioactive and fissile materials transport, in order that man and environment do not undergo the nuisances. The control of the safety is within the competence of the Asn. (N.C.)

Comparative approach between nuclear safety and security; Approche comparative entre surete et securite nucleaires

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-04-15

Adopting the definition of nuclear safety and nuclear security as they are specified by IAEA glossaries, this report first outlines that these both notions refer to similar risks but with causes of different nature. They discuss the notions of transparency and confidentiality and outline that security and safety both aims at the protection of population and of the environment. They discuss their organisational principles, notice that both have their own legal and regulatory framework, that authorities have expertise on both, that the responsibility is distributed among operators and the State, and that safety and security cultures are complementary. They analyse the design, exploitation and management principles of security and safety approaches: graded approach, defence-in-depth, synergy between security and safety, same daily monitoring requirement, same necessity to address the return on experience, same need to update a referential, a more constrained exchange of good practices in safety, a necessity to deal with their respective requirements, elaboration of emergency plans, performance of exercises

Annual report ''nuclear safety in France''; Le rapport annuel ''la surete nucleaire en France''

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

This document is the 2001 annual report of the French authority of nuclear safety (ASN). It summarizes the highlights of the year 2000 and details the following aspects: the nuclear safety in France, the organization of the control of nuclear safety, the regulation relative to basic nuclear facilities, the control of facilities, the information of the public, the international relations, the organisation of emergencies, the radiation protection, the transport of radioactive materials, the radioactive wastes, the PWR reactors, the experimental reactors and other laboratories and facilities, the nuclear fuel cycle facilities, and the shutdown and dismantling of nuclear facilities. (J.S.)

Statement of the IRSN on the safety re-examination assessment made by EDF within the frame of the third decennial inspection of the 900 MW reactors

International Nuclear Information System (INIS)

2008-01-01

The IRSN (the French Institute of Radioprotection and Nuclear Safety) here presents an assessment of the studies performed by EDF within the frame of the safety re-examination associated to the third decennial inspections of the 900 MW reactors, and of the modifications resulting from these studies with respect to the originally defined objectives of this re-examination. The aim of this report is to allow the ASN (Autorite de Surete Nucleaire, the Nuclear Safety Authority) stating the 900 MW reactor ability to carry on their operation until the fourth decennial inspections. Different themes and studies are assessed: internal and external aggressions (flooding, explosions, fire, seismic control, and climatic aggressions), accident assessments and their radiological consequences (failure of various components, the performing of probabilistic studies, confining procedures, structures and devices, etc.), operation and design of various systems and of civil engineering works. Several documents or extracts of official reports are given in appendix, expressing notably various recommendations on the here-above topics

The action of the project coordinator with respect to reactor safety

International Nuclear Information System (INIS)

Leclercq, Jacques

1981-01-01

Before describing the various actions of the project coordinator (EDF) entrusted with the building of nuclear power stations, with respect to reactor safety in France, the definition of reactor safety and the various participants are mentioned first. These participants are: the Government Departments and the Experts involved (the Department of Nuclear Safety of the 'Institut de Protection et de Surete Nucleaire' forming the first technical support) and the applicant, namely the EDF. The reactor safety actions of the project coordinator are defined as from the following components: 1 - The targets laid down with respect to safety, the final objective being the protection of workers and the public against the potential dangers of the installations, principally against radiation. 2 - The safety methodology at the design stage of the power station: 'barrier' method, defence method in depth at three levels, lines of assurance method, and probabilistic method. 3 - Safety actions at the construction stage within the context of an assurance of quality programe. 4 - Safety at the trials, commissioning and operating stage, with the backing of the 'Groupe Operationnel de Demarrage (G.O.D.)' and the 'Commission d'Essais sur Site (C.E.S.)'. An initial balance sheet of the reactor safety actions for the PWR units built by the EDF is presented [fr

Status and prospects of safety research about fuel cycle facilities in France

International Nuclear Information System (INIS)

Auchere, H.; Mercier, J.P.

1996-01-01

Although there is a good knowledge of the risks and no major accident occurred in France, as in other OECD countries, it remains useful to complete basic knowledge and to allow the quality of fuel cycle plants safety assessments to be improved further, particularly in countries equipped with a 'complete' nuclear fuel cycle (France, Japan and U.K.). The scope of the current and future IPSN ('Institut de Protection et de Surete Nucleaire': institute for protection and nuclear safety) research deals with the whole fuel cycle. The overview presented here in NUCEF'95 symposium contains a number of specific themes, some of which have already been started. Successful conclusion of the safety researches will allow the IPSN to have a more precise understanding about specific phenomena and notably to replace 'engineer judgements', though they may be based on a lot of experience and competence, by more scientifically established basic data. (J.P.N.)

SIPA, a PWR simulator for post-accident training and studies

International Nuclear Information System (INIS)

Peltier, J.; Poizat, F.

1990-01-01

SIPA (Simulator for Post-Accident conditions) which is now under development will be operated by EDF and CEA. Each organization will have its own version, SIPA 1 for EDF and SIPA 2 for CEA. The three main purposes will meet the needs of EDF and CEA as described below: - training of the EDF's ISR (Ingenieurs de Surete et Radioprotection = Shift Safety Advisors) which needs physical relevance, real time during accidental transients and visualisation of two-phase flow phenomena to well understand what could physically happen, - studies for EDF's designs which require calculation of a lot of points or scenarios. Quality Assurance of the models and data package, interactivity for procedure finalisation, availability of resources to all engineers, and possibility of creation of new models, - safety analysis requirements for CEA/IPSN (technical support of the French safety authority, the Central Service for the Safety of Nuclear Installations) which includes the actual safety analysis (analysis of procedures, design basis accidents, probabilistic safety analysis, real incidents studies, reactor tests...), the preparation and the execution of safety drills and training of engineer analysts

Criticality Experiments Performed in Saclay and Valduc Centers, France (1958-2002)

International Nuclear Information System (INIS)

Barbry, F.; Grivot, P.; Girault, E.; Fouillaud, P.; Cousinou, P.; Poullot, G.; Anno, J.; Bordy, J.M.; Doutriaux, D.

2003-01-01

Since 1958, the Commissariat a l'Energie Atomique and then the Institut de Radioprotection et de Surete Nucleaire (previously the Institut de Protection et de Surete Nucleaire) have carried out criticality experiments first in Saclay and then in the Valduc criticality laboratory. This paper is a survey of the programs conducted during the last 45 yr with the different apparatuses. This paper also gives information about plans for the future. Programs are presented following the chronology and the International Criticality Safety Benchmark Evaluation Project classification. Among the numerous series of experiments, now 22 series (corresponding to 407 configurations) have been included in the 'International Handbook of Evaluated Criticality Safety Benchmark Experiments'

Expert system for the investigation of safety system availability on a 900 MWe PWR

International Nuclear Information System (INIS)

Chauliac, C.; Deplanque, B.; To, L.H.

1988-01-01

A computer program of the expert system type would appear to be an elegant and effective tool for rapid diagnosis of safety system availability in accident situations. The expert system developed for this purpose by the Institut de Protection et de Surete Nucleaire (Institute for Nuclear Safety and Protection) has been described in this paper; its logic process has been examined in detail and illustrated by means of two examples. In its present form, this expert system monitors the availability of 21 main systems. In its final form (1989), 37 main systems will be tested. It will then include descriptions of between 1500 and 2000 objects and will utilize about 1000 rules. It will be run (as is presently the case) in a workstation with windowing facilities and graphic result displays which provide the highest degree of user-friendliness

Squale: evaluation criteria of functioning safety; Squale: criteres d`evaluation de la surete de fonctionnement

Energy Technology Data Exchange (ETDEWEB)

Deswarte, Y; Kaaniche, M [Centre National de la Recherche Scientifique (CNRS), 31 - Toulouse (France). Laboratoire d` Analyse et d` Architecture des Systemes; Corneillie, P [CE2A-DI, 92 - Courbevoie (France); Benoit, P [Matra Transport International, 92 - Montrouge (France)

1998-05-01

The SQUALE (security, safety and quality evaluation for dependable systems) project is part of the ACTS (advanced communications, technologies and services) European program. Its aim is to develop confidence evaluation criteria to test the functioning safety of systems. All industrial sectors that use critical applications (nuclear, railway, aerospace..) are concerned. SQUALE evaluation criteria differ from the classical evaluation methods: they are independent of the application domains and industrial sectors, they take into account the overall functioning safety attributes, and they can progressively change according to the level of severity required. In order to validate the approach and to refine the criteria, a first experiment is in progress with the METEOR automatic underground railway and another will be carried out on a telecommunication system developed by Bouygues company. (J.S.) 15 refs.

Science for safety in nuclear waste handling; Aspects scientifiques de la surete des dechets radioactifs

Energy Technology Data Exchange (ETDEWEB)

Bonin, B. [CEA Saclay, Dir. de l' Energie Nucleaire (DEN), 91 - Gif sur Yvette (France)

2005-05-01

A facility for disposing of nuclear waste has the objective of protecting mankind. It is shown how nuclear safety is taken into account in the definition of the facilities, particularly through the use of the multi-barriers concept. Elements on safety assessment are provided, with emphasis on the scenario (normal or altered approach; examples of research programs required by these assessment tasks, particularly by means of underground laboratories are given. (author)

Organizing a complex transport while guaranteeing safety and transparency: the example of vitrified wastes sent back to Germany

International Nuclear Information System (INIS)

Krochmaluk, Julie; Lebrun, Marc; Delmestre, Alain; Barbey, Pierre; Bonvalot, Vanessa; Belleville, Didier; Rollinger, Patrice; Alter, Ulrich

2012-01-01

This chapter is made of several small articles entitled: - 'Les controles avant le depart du convoi franco-allemand' (Controls before the departure of the French-German convoy); - 'La supervision des transports de matieres radioactives: une approche extensive de la surete des operations' (The supervision of radioactive material transports: an extended approach of operation safety); - 'Le dispositif d'information du public sur le transport des substances radioactives mis en place par l'ASN' (The plan implemented by the ASN for public information on nuclear materials transport); - 'Le recours de l'ASN a l'expertise de l'ACRO sur le convoi de colis de dechets vitrifies vers l'Allemagne' (The appeal of the ASN to the ACRO's expertise on the vitrified parcel convoy to Germany); - 'La participation du collectif STOP-EPR a l'inspection de l'ASN du convoi de colis de dechets vitrifies vers l'Allemagne' (The participation of the STOP-EPR collective to the control by the ASN of the vitrified parcel convoy to Germany); - 'La securite et la surete: des valeurs que le Groupe SNCF partage' (Security and safety: values which are shared by the SNCF Group); - 'Le transport de matieres nucleaires entre la France et l'Allemagne au cours des 40 dernieres annees' (Transport of nuclear materials between France and Germany during the last 40 years). Addressing the case of vitrified wastes transported back to Germany, the articles indicate the controls performed in France before convoy departure, discuss the approach adopted for the safety of radioactive material transport, comment the management of public information by the ASN for such transports, comment the intervention of the ACRO (Association for the control of radioactivity in western France) on the request of the ASN and the participation of a collective group (STOP-EPR) to the inspection of a convoy, outline the commitment of the French Railways (SNCF) in terms of security and safety, and give a qualitative and quantitative

Safety of the pressure vessels of water reactors. Prevention of sudden failure

International Nuclear Information System (INIS)

Petrequin, P.; Barrachin, B.

1975-01-01

From the safety view point the primary circuit is considered as the essential barrier against the diffusion of radioactive products in the event of fuel element failure. The safety of the vessel itself, the failure of which is not accounted for in accident analyses, is based chiefly on a series of preventive measures such as the suitable choice of materials and manufacturing process, compliances with detailed specifications concerning tests and defect tolerances, supervision in service. All these points are examined in detail when the safety analysis is performed. In this context the Service de Recherches Metallurgiques Appliquees assists the Department de Surete Nucleaire in the study of special problems such as the prevention of sudden failure and the characterisation of steels as a function of working conditions, particularly neutron irradiation. The report is thus devoted mainly to the presentation of methods to prevent sudden failure, with special emphasis on the limits of application. Some results obtained at the Service de Recherches Metallurgiques Appliquees on steels typical of those used for water reactor vessels (A533 and A508Cl.3) are given by way of example. Part two concentrates on the role of various factors influencing embrittlement by irradiation [fr

Operation safety of control systems. Principles and methods; Surete de fonctionnement des systemes de commande. Principes et methodes

Energy Technology Data Exchange (ETDEWEB)

Aubry, J.F. [Institut National Polytechnique, 54 - Nancy (France); Chatelet, E. [Universite de Technologie de Troyes, 10 (France)

2008-09-15

This article presents the main operation safety methods that can be implemented to design safe control systems taking into account the behaviour of the different components with each other (binary 'operation/failure' behaviours, non-consistent behaviours and 'hidden' failures, dynamical behaviours and temporal aspects etc). To take into account these different behaviours, advanced qualitative and quantitative methods have to be used which are described in this article: 1 - qualitative methods of analysis: functional analysis, preliminary risk analysis, failure mode and failure effects analyses; 2 - quantitative study of systems operation safety: binary representation models, state space-based methods, event space-based methods; 3 - application to the design of control systems: safe specifications of a control system, qualitative analysis of operation safety, quantitative analysis, example of application; 4 - conclusion. (J.S.)

The transport safety of radioactive matters; La surete des transports des matieres radioactives

Energy Technology Data Exchange (ETDEWEB)

Landier, D.; Louet, Ch.A.; Robert, Ch. [Autorite de Surete Nucleaire, 75 - Paris (France); Binet, J. [Commission europeenne, DG Energie et transports, Bruxelles (Belgium); Malesys, P. [TN International, 75 - Paris (France); Pourade, C. [Societe Dangexpress, 78 - St Remy l' Honore (France); Le Meur, A.; Robert, M. [Societe Nationale des Chemins de fer Francais, 75 - Paris (France); Turquet de Beauregard, G.Y.; Hello, E. [CIS bio, 91 - Gif sur Yvette (France); Laumond, A. [Electricite de France (EDF), 75 - Paris (France); Regnault, Ph.; Gourlay, M. [AREVA NC, 78 - Velizy Villacoublay (France); Bruhl, G. [CEA Fontenay-aux-Roses, Dir. de la Protection et de la Surete Nucleaire, 92 (France); Malvache, P.; Dumesnil, J. [CEA Saclay, Dir. de l' Energie Nucleaire (DEN), 91 - Gif sur Yvette (France); Cohen, B. [Agence Nationale pour la Gestion des Dechets Radioactifs (ANDRA), 92 - Chatenay Malabry (France); Sert, G. [Institut de Radioprotection et de Surete Nucleaire (IRSN), 92 - Clamart (France); Pain, M. [Ministere de l' Interieur, et de l' Amenagement du Territoire, Dir. de la Defense et la Securite Civiles, 75 - Paris (France); Green, L.; Hartenstein, M. [World Nuclear Transport Institute, London (United Kingdom); Stewart, J. [Ministere des Transport, Royaume Uni (United Kingdom); Cottens, E.; Liebens, M. [Agence Federale de Controle Nucleaire (Belgium); Marignac, Y. [Wise, 75 - Paris (France)

2007-02-15

Since the control of transport of radioactive materials was given to A.S.N. 10 years ago, A.S.N. has strengthened the radioactive material transport inspections, in particular of the designers, manufacturers, carriers and consignors. A.S.N. has implemented INES scale for incidents during transport. It has participated as much as possible to IAEA working groups in order to improve the international regulatory framework. And, supported by I.R.S.N., A.S.N. has performed a periodic safety review of existing package models and has approved new models incorporating innovative design features. Finally, A.S.N. has tested its emergency responses to procedures to an accident involving the transport of radioactive materials. All these actions taken together have led to improvement in and reinforcement of the safety culture among the transport operators; this has been acknowledged by a recent audit T.R.A.N.S.A.S. performed by IAEA. In spite of all these actions, there are not approved by the competent authority. As A.S.N. is in charge of every field in radioprotection, this should help to intensify the control. In addition, the different kinds of transport are also tackled as rail transport with S.N.C.F. radiological risk training, air transport through nuclear medicine. Some experience feedback are given such radioactive waste transport to the storage facilities in the Aube or how to protect the population after a nuclear transport incident with the O.R.S.E.C.-T.M.S. plans. (N.C.)

Basic safety rule number no.2002-01; Regle fondamentale de surete no. 2002-01

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-12-15

The purpose of this rule is to define acceptable methods for the development of probabilistic safety assessments(P.S.A.) and proven applications of P.S.A. for operating or future pressurized water reactors (PWR type reactors) of the French nuclear power programme, incorporating available French and international experience in this area. The standing group of experts for nuclear reactors has been consulted for the drafting of this rule. (N.C.)

Contributions to safety studies for new concepts of nuclear reactors; Contributions aux etudes de surete pour des filieres innovantes de reacteurs nucleaires

Energy Technology Data Exchange (ETDEWEB)

Perdu, F

2003-12-01

The complete study of molten salt reactors, designed for a massive and durable nuclear energy production, must include neutronics, hydraulics and thermal effects. This coupled study, using the MCNP and Trio{sub U} codes, is undertaken in the case of the MSRE (molten salt reactor experiment) prototype. The obtained results fit very well the experiment. Their extrapolation suggests ways of improving the safety coefficients of power molten salt reactors. A second part is devoted to accelerator driven subcritical reactors, developed to incinerate radioactive waste.We propose a method to measure the prompt reactivity from the decay following a neutron pulse. It relies only on the distribution of times between generations, which is a characteristic of the reactor. This method is implemented on the results of the MUSE 4 experiment, and the obtained reactivity is accurate within 5%. (author)

2005 dossier: granite. Tome: safety analysis of the geologic disposal; Dossier 2005: granite. Tome analyse de surete du stockage geologique

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-07-01

This document makes a status of the researches carried out by the French national agency of radioactive wastes (ANDRA) about the safety aspects of the geologic disposal of high-level and long-lived (HLLL) radioactive wastes in granite formations. Content: 1 - safety approach: context and general goal, references, design approach by safety functions, safety approach during the construction-exploitation-observation-closure phase, safety analysis during the post-closure phase; 2 - general description: HLLL wastes, granitic environment, general structure of the architecture of a disposal facility; 3 - safety functions and disposal design: general context, safety functions of the long-term disposal, design dispositions retained to answer the functions; 4 - operational safety: people's protection, radiological risks during exploitation, risk analysis in accident situation; 5 - qualitative safety analysis: methodology, main results of the analysis of the features, events and processes (FEP) database; 6 - disposal efficiency evaluation during post-closure phase: calculation models, calculation tools used for the modeling of radionuclides transport, calculation results and main lessons. (J.S.)

2005 dossier: granite. Tome: safety analysis of the geologic disposal; Dossier 2005: granite. Tome analyse de surete du stockage geologique

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-07-01

This document makes a status of the researches carried out by the French national agency of radioactive wastes (ANDRA) about the safety aspects of the geologic disposal of high-level and long-lived (HLLL) radioactive wastes in granite formations. Content: 1 - safety approach: context and general goal, references, design approach by safety functions, safety approach during the construction-exploitation-observation-closure phase, safety analysis during the post-closure phase; 2 - general description: HLLL wastes, granitic environment, general structure of the architecture of a disposal facility; 3 - safety functions and disposal design: general context, safety functions of the long-term disposal, design dispositions retained to answer the functions; 4 - operational safety: people's protection, radiological risks during exploitation, risk analysis in accident situation; 5 - qualitative safety analysis: methodology, main results of the analysis of the features, events and processes (FEP) database; 6 - disposal efficiency evaluation during post-closure phase: calculation models, calculation tools used for the modeling of radionuclides transport, calculation results and main lessons. (J.S.)

Classification of mechanical components electrical systems and civil works structures

International Nuclear Information System (INIS)

1984-12-01

RFS or Regles Fondamentales de Surete (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety, while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the Service Central de Surete des Installations Nucleaires, or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary, any RFS and specify, if need be, the terms under which a modification is deemed retroactive. The purpose of this RFS is to define the various classifications used in French regulatory practice with regard to safety

Radioecological studies tied to the French nuclear power station programme: aims, nature and mode of execution

International Nuclear Information System (INIS)

Delile, G.

1980-01-01

Under present French practice, assessing the effects of radioactive discharges due to the various likely accident situations comes under 'L'Analyse de Surete Nucleaire' (Nuclear Safety Analysis). The assessment of radioactive discharges relating to normal working comes within the framework of radioecologic studies. Radioecology studies are undertkaen for every power station project. They consist in: - studying what is to be done with radioelements discharged as liquids or gases, - estimating their impact on the populations in the areas of influence of the power station and checking that this impact is permissible, - establishing a surveillance measuring programme for checking against the predictions made and, if required, determining the modifications to be made to the facilities or to their method of operation [fr

General rules applicable to civil works

International Nuclear Information System (INIS)

1981-07-01

RFS or Regles Fondamentales de Surete (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety, while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the Service Central de Surete des Installations Nucleaires, or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary, any RFS and specify, if need be, the terms under which a modification is deemed retroactive. For civil works, the use of the RCC. G (Design and Construction Rules for Civil works of 900 MWe PWR Nuclear Power Plants) is accepted with conditions described in this RFS

Meteorological instrumentation

International Nuclear Information System (INIS)

1982-06-01

RFS or ''Regles Fondamentales de Surete'' (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety , while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the ''Service Central de Surete des Installations Nucleaires'' or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary any RFS and specify, if need be, the terms under which a modification is deemed retroactive. The purpose of this RFS is to specify the meteorological instrumentation required at the site of each nuclear power plant equipped with at least one pressurized water reactor

Design of the containment spray system

International Nuclear Information System (INIS)

1985-12-01

RFS or Regles Fondamentales de Surete (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety, while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the Service Central de Surete des Installations Nucleaires, or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary, any RFS and specify, if need be, the terms under which a modification is deemed retroactive. The present RFS defines the functional requirements of the containment spray system and proposes certain complementary criteria or methods to be used in its equipment design

R and D on support to ITER safety assessment

International Nuclear Information System (INIS)

Van Dorsselaere, J.P.; Perrault, D.; Barrachin, M.; Bentaib, A.; Bez, J.; Cortes, P.; Seropian, C.; Tregoures, N.; Vendel, J.

2009-01-01

After performing its first ITER safety assessment in 2002 on behalf of the French 'Autorite de Surete Nucleaire (ASN)', the French 'Institut de Radioprotection et de Surete Nucleaire (IRSN)' is now analysing the new ITER Fusion facility safety file. The operator delivered this file to the ASN as part of its request for a creation decree, legally necessary before building works can begin on the site. The IRSN first task in following ITER throughout its lifetime is to study the safety approach adopted by the operator and the associated issues. Such a challenging new technology calls for further in-house expertise and so in parallel a R and D program has been set up to support this safety assessment process, now and in the next years. Its main objectives are to identify the key parameters for mastering some risks (that would have been insufficiently justified by the operator) and to perform some verifications with methods and codes independent from the operator's ones. Priority has been given to four technical issues (others could be investigated in the future, like the behaviour of activated corrosion products). The first issue concerns the simulation of accident sequences with the help of the ASTEC European system code, developed by IRSN (jointly with its German counterpart, the GRS) for severe accidents in Pressurised Water Reactors. A preliminary analysis showed that most of its physical models are already applicable, e.g., for thermal-hydraulics in accidents caused by water or air ingress into the vacuum vessel (VV) or dust transport. Work has started in 2008 on some model adaptations, for instance oxidation of VV first wall materials by steam or air, and on validation on the ITER-specific ICE and LOVA experiments. Other model improvements are planned in the next years, as feedback from the work done for the other technical issues and from the code validation. The second issue concerns the risk of gas explosion due to concentrations of hydrogen and carbon

Seismic instrumentation

International Nuclear Information System (INIS)

1984-06-01

RFS or Regles Fondamentales de Surete (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety, while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the Service Central de Surete des Installations Nucleaires, or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary, any RFS and specify, if need be, the terms under which a modification is deemed retroactive. The aim of this RFS is to define the type, location and operating conditions for seismic instrumentation needed to determine promptly the seismic response of nuclear power plants features important to safety to permit comparison of such response with that used as the design basis

General rules applicable to quality assurance

International Nuclear Information System (INIS)

1981-11-01

RFS or Regles Fondamentales de Surete (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety, while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the Service Central de Surete des Installations Nucleaires, or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary, any RFS and specify, if need be, the terms under which a modification is deemed retroactive. The aim of this rule is to define a series of measures to meet these general regulatory equipments. By applying this rule, the quality assurance code of practice for nuclear power plant safety, established by the International Atomic Energy Agency (I.A.E.A.), is considered to be observed

Organizations putting in place in case of accident in a french nuclear power plant

International Nuclear Information System (INIS)

Noc, B.; Queniart, D.

1987-01-01

In case of accident entraining radiological consequences on or near the site of nuclear power reactor, organizations are putting in place. These organizations include as well as side of operating authority (generally Electricite de France) or public organizations including safety organizations (Service Central de Surete des Installations Nucleaires, Institut de Protection et de Surete Nucleaire), one local organization and one centralized national organization. Informations exchange and coordination necessary between these organizations are governed by protocols. These protocols include particularly, the problems of mobilizing experts and of dealing with the saturation of normal telecommunications channels. The lessons acquired during accident simulation exercises carried out in recent years are progressively put in place in these protocols [fr

History of nuclear power plants safety in France (1945-2000) - Engineer techniques, expert evaluation, topical issue

International Nuclear Information System (INIS)

Foasso, Cyrille

2003-01-01

This doctoral dissertation relates the history of the mastery of risks in civil nuclear plants in France. Since 1960, it's known as the 'surete nucleaire'. Over a fifty-year period separating the discovery or the atomic fission and its industrial application on a large scale this PhD shows which technical means were used over the years by engineers to handle this risk which is said to be huge. It also studies the various processes in expert evaluation and in decision making elaborated to evaluate if the risk was acceptable or not. Beyond the conflicts between nuclear advocates and opponents, this thesis shows how ever among nuclear engineer the growing distinction between roles (promoters, experts and controlling authorities) and the various jobs (designers, builders and plant operators) triggered different estimations as far as the methods to obtain a satisfactory safety. Thanks to the progress of knowledge through research programs, thanks to the lessons drawn from the functioning or dysfunction of nuclear plants, thanks to the reinforcement of regulations (which more or less reflects the public's opinion concerning this industry) the safety has progressively improved. Thus, this historical study is multiple: a technical history of technology, a history of scientific, industrial and administrative organization, a social history and finally an international and comparative history since the nuclear energy history quickly developed beyond national boundaries. (author) [fr

Evaluation of potential hazards presented by the nearby industrial environment and transportation routes

International Nuclear Information System (INIS)

1982-05-01

RFS or Regles Fondamentales de Surete (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety, while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the Service Central de Surete des Installations Nucleaires, or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary, any RFS and specify, if need be, the terms under which a modification is deemed retroactive. The purpose of this RFS is to define methods for determining risks created by potential hazards represented by the industrial environment and transportation routes in the vicinity of a PWR, in order to verify design criteria acceptability with regard to such hazards

Civil Works Seismic Designs

International Nuclear Information System (INIS)

1985-12-01

RFS or Regles Fondamentales de Surete (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety, while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the Service Central de Surete des Installations Nucleaires, or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary, any RFS and specify, if need be, the terms under which a modification is deemed retroactive. This rule defines: - the parameters characterizing the design seismic motions - the calculation methods - the mathematical schematization principles on which calculations are based - the use of the seismic response for the structure checking - the content of the documents to be presented

Hazards related to external flooding

International Nuclear Information System (INIS)

1984-04-01

RFS or Regles Fondamentales de Surete (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety, while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the Service Central de Surete des Installations Nucleaires, or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary, any RFS and specify, if need be, the terms under which a modification is deemed retroactive. This RFS is intended to give state-of-the-art definitions of: - an acceptable method to determine water levels to be used in flood design of a facility - facility design principles required to meet the principles above

Studies about pressure variations and their effects during a fire in a confined and forced ventilated enclosure: safety consequences in the case of a nuclear facility

International Nuclear Information System (INIS)

Hugues Pretrel; Laurent Bouilloux; Jerome Richard

2005-01-01

Full text of publication follows: In a nuclear facility, the cells are confined and forced ventilated and some of them are equipped with isolation devices designed to close in case of a fire. So, if a fire occurred, the pressure variations in the cell could be important. This contribution presents the safety concerns related to pressure variation effects (propagation of smokes and/or flames through the fire barriers, propagation of radioactive material) and the research works carried out by the french 'Institut de Radioprotection et de Surete Nucleaire' (IRSN) on this topic. These research works are composed of two different studies. The first study permits to quantify the overpressure and depression levels and to reveal the influence of the fire heat release rate (HRR), of the characteristics of the cell, of the ventilation layout (especially the airflow resistances of the ventilation branches) and of the control of the fire dampers. This study is based on three sets of experimental tests performed in three large-scale facilities of various dimensions (3600 m3, 400 m3 and 120 m3 in volume) and with several settings of the ventilation network. The analysis focuses on the conditions that lead to significant overpressure and depression peaks and identifies the level of fire HRR and airflow resistances for which pressure peaks may become a safety concern. The second study allows to characterise the behaviour of sectorisation and containment equipments subject to pressure stresses. The mechanical resistance of some equipments (doors, fire dampers) subject to pressure stresses as well as the aeraulic behaviour of this equipment (gas leak rates) are determined in order to assess the potential transfer of contamination in the ventilation networks. (authors)

French regulation and waste management

International Nuclear Information System (INIS)

1984-08-01

The organization and the role played by French safety authorities for waste management are described. The French policy for storage and conditioning: basic objectives and waste management optimization are specified. Safety requirements are based on the barrier principle, they are mentioned for packaging and storage. The ''Institut de Protection et Surete Nucleaire'' deals not only with safety analysis but also help the ''autorites ministerielles'' for the development of fundamental safety rules. Examples for spent fuel storage and radioactive materials transport are treated in appendixes [fr

Status of safety at Areva group facilities. 2006 annual report; Etat de surete des installations nucleaires. Rapport annuel 2006

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-07-01

This report presents a snapshot of nuclear safety and radiation protection conditions in the AREVA group's nuclear installations in France and abroad, as well as of radiation protection aspects in service activities, as identified over the course of the annual inspections and analyses program carried out by the General Inspectorate in 2006. This report is presented to the AREVA Supervisory Board, communicated to the labor representation bodies concerned, and made public. In light of the inspections, appraisals and coordination missions it has performed, the General Inspectorate considers that the nuclear safety level of the AREVA group's nuclear installations is satisfactory. It particularly noted positive changes on numerous sites and efforts in the field of continuous improvement that have helped to strengthen nuclear safety. This has been possible through the full involvement of management teams, an improvement effort initiated by upper management, actions to increase personnel awareness of nuclear safety culture, and supervisors' heightened presence around operators. However, the occurrence of certain events in facilities has led us to question the nuclear safety repercussions that the changes to activities or organization on some sites have had. In these times of change, drifts in nuclear safety culture have been identified. The General Inspectorate considers that a preliminary analysis of the human and organizational factors of these changes, sized to match the impact the change has on nuclear safety, should be made to ensure that a guaranteed level of nuclear safety is maintained (allowance for changes to references, availability of the necessary skills, resources of the operating and support structures, etc.). Preparations should also be made to monitor the changes and spot any telltale signs of drift in the application phase. Managers should be extra vigilant and the occurrence of any drift should be systematically dealt with ahead of

Inter-CLI work-group: safety after Fukushima; GT inter-CLI 'surete post Fukushima'

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-11-03

This document contains a whole set of questions asked about nuclear safety and security by a work-group made of members of associations belonging to local information commissions. These questions are asked either to the French State, or to EDF, or to AREVA. They bear on general issues common to La Hague and Flamanville nuclear installations, notably public information, emergency plans, post-accident management, subcontracting, loss of electricity supply, public health, governance, computer hacking, extreme meteorological events. A set of questions concerns the AREVA processing plant in La Hague (warehousing, pools for irradiated fuels, plutonium oxide storage and warehousing, and so on), and another set concerns the Flamanville nuclear power plant (different aspects of the management of a crisis situation). The last set of questions concerns the Manche nuclear waste storage centre

Status of safety at Areva group facilities. 2007 annual report; Areva, etat de surete des installations nucleaires. Rapport annuel 2007

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

This report describes the status of nuclear safety and radiation protection in the facilities of the AREVA group and gives information on radiation protection in the service operations, as observed through the inspection programs and analyses carried out by the General Inspectorate in 2007. Having been submitted to the group's Supervisory Board, this report is sent to the bodies representing the personnel. Content: 1 - A look back at 2007 by the AREVA General Inspector: Visible progress in 2007, Implementation of the Nuclear Safety Charter, Notable events; 2 - Status of nuclear safety and radiation protection in the nuclear facilities and service operations: Personnel radiation protection, Event tracking, Service operations, Criticality control, Radioactive waste and effluent management; 3 - Performance improvement actions; 4 - Description of the General Inspectorate; 5 - Glossary.

IPSN activity report 1999

International Nuclear Information System (INIS)

2000-01-01

The IPSN (Institut de Protection et de Surete Nucleaire) carries out for the Government, studies and inspections on nuclear installations at many life steps (design, realisation, exploitation, shutdown and dismantling). To obtain quality researches, the Institut performs studies in all domains concerned by the safety and its improvement. The main projects of the year 1999, in the following topics are presented: the nuclear installations and the radioactive wastes safety, the crisis and nuclear materials management, the human and the environment protection, the international activities and cooperation, the quality insurance. It provides also information on the cooperation, the budget, the human resource policy and the communication activities. (A.L.B.)

IPSN activity report 1999; Rapport d'activite de l'IPSN 1999

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-07-01

The IPSN (Institut de Protection et de Surete Nucleaire) carries out for the Government, studies and inspections on nuclear installations at many life steps (design, realisation, exploitation, shutdown and dismantling). To obtain quality researches, the Institut performs studies in all domains concerned by the safety and its improvement. The main projects of the year 1999, in the following topics are presented: the nuclear installations and the radioactive wastes safety, the crisis and nuclear materials management, the human and the environment protection, the international activities and cooperation, the quality insurance. It provides also information on the cooperation, the budget, the human resource policy and the communication activities. (A.L.B.)

IPSN activity report 1999; Rapport d'activite de l'IPSN 1999

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-07-01

The IPSN (Institut de Protection et de Surete Nucleaire) carries out for the Government, studies and inspections on nuclear installations at many life steps (design, realisation, exploitation, shutdown and dismantling). To obtain quality researches, the Institut performs studies in all domains concerned by the safety and its improvement. The main projects of the year 1999, in the following topics are presented: the nuclear installations and the radioactive wastes safety, the crisis and nuclear materials management, the human and the environment protection, the international activities and cooperation, the quality insurance. It provides also information on the cooperation, the budget, the human resource policy and the communication activities. (A.L.B.)

Physics related to control and safety of hybrid systems; Physique associee au controle et a la surete des systemes hybrides

Energy Technology Data Exchange (ETDEWEB)

Gueton, O

2001-12-01

Regarding nuclear waste management, ADS can be considered as large minor actinides burners. In a first part, a critical analysis of different reactor types shows that fast spectrum, helium coolant and nitride fuel, containing 100% minor actinides, agree perfectly with the high transmutation requirements of ADS. The control and safety demonstration of this system represents the main purpose of this study. Understanding spatial and dynamic behaviour of ADS flux is absolutely necessary. For this purpose, we have defined an indicator to quantify spatial decoupling. It shows, on the one hand, point kinetic deficiency to study local transients, and on the other hand, perturbations propagation differences between ADS and critical cores. Then, in a more concrete approach, accidental sequences (source transient, beam de-focalization, reactivity insertions, loss of flow, depressurization) are evaluated for this core, strongly loaded with minor actinides. It is shown that the automatic beam shutdown leads to preserve large safety margins for all studied transients. The accelerator emergency stop is induced by an unexpected evolution of the core control parameters. These parameters, except reactivity, can be directly measured in subcritical systems like in critical ones. Concerning reactivity, we suggest a new method for its absolute determination in ADS: at the time of reactor start-up, the reactivity must be calibrated by coupling two methods of relative reactivity measurements (pulsed source and Approached Source Multiplication) for successive subcritical levels. After that, the on-line follow-up of reactivity is obtained from this calibration like in a critical core. (authors)

Simulation of power excursions - Osiris reactor; Simulation des excursions de puissance - pile Osiris

Energy Technology Data Exchange (ETDEWEB)

Pascouet, A [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1964-07-01

Following the experimental work accomplished in the U.S.A. on Borax 1 and SPERT 1 and the accident of SL 1, the 'Commissariat a l'Energie Atomique' started a research program about the safety of its own swimming Pool reactors, with regard to power excursions. The first research work led to the design of programmed explosive charges, adapted to the simulation of a power excursion. This report describes the application of these methods to the investigation of Osiris safety. (author) [French] A la suite des essais effectues aux U.S.A. sur BORAX 1 et SPERT 1 et de l'accident survenu a SL 1, le Commissariat a l'Energie Atomique a lance un programme d'etudes sur la surete de ses reacteurs piscines vis-a-vis des excursions de puissance. Les premieres etudes ont abouti A la mise au point de charges programmees capables de simuler une excursion de puissance. On trouvera dans le present rapport l'application de ces methodes a l'etude de la surete d'OSIRIS. (auteur)

Evaluation of feed and bleed cooling mode in case of total loss of feedwater on 900 MWe PWR

International Nuclear Information System (INIS)

Champ, M.; Cornille, Y.

1989-07-01

The physical studies carried out with the CATHARE code to assess the feed and bleed procedure developed in order to cope with the total loss of feed water on a 900 MWe PWR are presented. These studies allowed the definition of the maximum delays of intervention which would prevent the core from uncovering. Different cases of equipment availability are considered. The data generated will be used in the 900 MWe Probabilistic Safety Assessment which is under way at the Institut de Protection et de Surete Nucleaire

IRSN 2009 annual report

International Nuclear Information System (INIS)

2010-01-01

This report gives an overview of the role, the missions and the activities of the IRSN (Institut de radioprotection et de surete nucleaire), the French public institution in charge of radioprotection and nuclear safety issues. After some data about its personnel and budget, the report presents the IRSN's organisation and its various activities in different fields: safety of existing installations, expertise for future installations (new generation reactors, waste storages), population and environment exposure, nuclear installation and material safety, facing the crisis, effects of chronic exposures, and radioprotection issues in the medical sector

Challenges for the nuclear safety of the deregulation of electricity markets; Defis pour la surete nucleaire de la dereglementation des marches de l'electricite

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

Eurosafe 2000 was organised around two round tables on the first day and four seminars on the second day. The first round table dealt with general aspects of deregulation including the economic constraints and the special challenges arising during transition from regulated to deregulated structures. The second round table focussed on technical and organisational safety issues which are directly or indirectly related to the changes introduced by deregulation. The four seminars hold in order to provide opportunities for comparing experiences and learning about recent activities of IPSN, GRS and their partners in the European Union and Eastern Europe: Seminar 1 (Nuclear installation safety, assessment and analysis): assessment of the flooding incident at the Blayais nuclear power plant; PSA data base, comparison of the French and German approach; assessment of the Balakovo fire probabilistic study and elaboration of a guide for reviewing fire PSA; comprehensive technical assessment of an advanced German PWR by PSA - objectives and main results; PSA approach for the safety assessment of low-power and shutdown states; correlation of initiating events with the PSA level-2 results; safety assessment for fission products tests in the Phebus reactor; use of NPP simulators for applied human factor studies; assessment of the 'deterministic realistic method' applied to large LOCA analysis; assessment of the feasibility of an improvement programme enabling operation of units 3 and 4 of Kozloduy nuclear power plant. Seminar 2 (nuclear installation safety, research): PHEBUS 2K project on severe accidents; current status of the COCOSYS development; fission product modeling in ASTEC; Euratom Framework Programme (FP) research in reactor safety: main achievements of FP- 4 (1994-1998), some preliminary results of FP-5 (1998-2002) and prospects for beyond 2002; development of coupled systems of 3D neutronics and fluid-dynamic system codes and their application for safety analyses

Progress report: nuclear safety and radiation protection in 2006; Rapport annuel: la surete nucleaire et la radioprotection en France en 2006

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

For the French Nuclear Safety Authority (Asn), the year 2006 was marked by two important nuclear laws being passed, one of which brought about a major change in its status. The year was a relatively satisfactory one with regard to nuclear safety, although the picture was more contrasted concerning radiation protection: in this area, more particularly in the medical field, the overall impression of good progress is offset by the declaration of a number of radiotherapy accidents. Given the benefits expected from radiotherapy treatment by the patient suffering from cancer, the conditions in which this activity is carried out are a subject of major concern for Asn, in the light of the serious risks linked to patient over-exposure. ( some important points as follows: the law on transparency and security in the nuclear field, the law on sustainable management of radioactive materials and waste, Asn: an independent administrative authority, EPR reactor project safety, I.R.R.S.: an international audit of Asn in 2006, harmonization of nuclear safety, cancer radiotherapy, improved information of the public after the T.S.N. law, taking account of organisational and human factors). (N.C.)

Development and experimental qualification of the new safety-criticality CRISTAL package; Developpement et qualification experimentale du nouveau formulaire de surete-criticite Cristal

Energy Technology Data Exchange (ETDEWEB)

Mattera, Ch

1998-11-01

This thesis is concerned with Criticality-Safety studies related to the French Nuclear Fuel Cycle. We first describe the steps in the nuclear fuel cycle and the specific characteristics of these studies compared with those performed in Reactor Physics. In order to respond to the future requirements of the French Nuclear Program, we have developed a new package CRISTAL based on a recent cross sections library (CEA 93) and the newest accurate codes (APOLLO 2, MORET 4, TRIPOLI 4). The CRISTAL system includes two calculations routes: a design route which will be used by French Industry (COGEMA/SGN) and a reference route. To transfer this package to the French industry, we have elaborated calculation schemes for fissile solutions, dissolver media, transport casks and storage pools. Afterwards, these schemes have been used for the CRISTAL experimental validation. We have also contributed to the CRISTAL experimental database by reevaluating a French storage pool experiment: the CRISTO II experiment. This revaluation has been submitted to the OECD working group in order that this experiment can be used by international criticality safety engineers to validate calculations methods. This work represents a large contribution to the recommendation of accurate calculation schemes and to the experimental validation of the CRISTAL package. These studies came up to the French Industry expectations. (author)

Safety study application guide

International Nuclear Information System (INIS)

1993-07-01

Martin Marietta Energy Systems, Inc., (Energy Systems) is committed to performing and documenting safety analyses for facilities it manages for the Department of Energy (DOE). Included are analyses of existing facilities done under the aegis of the Safety Analysis Report Upgrade Program, and analyses of new and modified facilities. A graded approach is used wherein the level of analysis and documentation for each facility is commensurate with the magnitude of the hazard(s), the complexity of the facility and the stage of the facility life cycle. Safety analysis reports (SARs) for hazard Category 1 and 2 facilities are usually detailed and extensive because these categories are associated with public health and safety risk. SARs for Category 3 are normally much less extensive because the risk to public health and safety is slight. At Energy Systems, safety studies are the name given to SARs for Category 3 (formerly open-quotes lowclose quotes) facilities. Safety studies are the appropriate instrument when on-site risks are limited to irreversible consequences to a few people, and off-site consequences are limited to reversible consequences to a few people. This application guide provides detailed instructions for performing safety studies that meet the requirements of DOE Orders 5480.22, open-quotes Technical Safety Requirements,close quotes and 5480.23, open-quotes Nuclear Safety Analysis Reports.close quotes A seven-chapter format has been adopted for safety studies. This format allows for discussion of all the items required by DOE Order 5480.23 and for the discussions to be readily traceable to the listing in the order. The chapter titles are: (1) Introduction and Summary, (2) Site, (3) Facility Description, (4) Safety Basis, (5) Hazardous Material Management, (6) Management, Organization, and Institutional Safety Provisions, and (7) Accident Analysis

Annual report ''nuclear safety in France''; Le rapport annuel ''la surete nucleaire en France''

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

This document is the 2001 annual report of the French authority of nuclear safety (ASN). It summarizes the highlights of the year 2000 and details the following aspects: the nuclear safety in France, the organization of the control of nuclear safety, the regulation relative to basic nuclear facilities, the control of facilities, the information of the public, the international relations, the organisation of emergencies, the radiation protection, the transport of radioactive materials, the radioactive wastes, the PWR reactors, the experimental reactors and other laboratories and facilities, the nuclear fuel cycle facilities, and the shutdown and dismantling of nuclear facilities. (J.S.)

The formal notices of the French authority of nuclear safety; Les mises en demeure de l'autorite de surete nucleaire

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

The French authority of nuclear safety (ASN) publishes on its web site (http://www.asn.gouv.fr) the formal notices and official statements addressed by the ASN to the concerned responsible persons (operators of nuclear facilities, directors of companies etc..) when anomalies requiring a corrective action have been noticed during on-site or off-site safety inspections. This document brings together the formal notices addressed by the ASN since June 2000 and up to April 2002. (J.S.)

The nuclear safety and the radiation protection in France in 2003; La surete nucleaire et la radioprotection en France en 2003

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-03-15

Nine points are reviewed: the law project relative to the safety and openness in nuclear field, the safety of the European PWR type Reactor, the priorities in radiation protection, inspection of radiation protection, the surveillance of patients exposure to ionizing radiations, the hot days and dryness of summer 2003 and the functioning of nuclear power plant, the national planning of radioactive waste management, the becoming of high level and years living radioactive waste, the European nuclear policy. (N.C.)

Development and experimental testing of the new safety-criticality Cristal package; Developpement et qualification experimentale du nouveau formulaire de surete-criticite Cristal

Energy Technology Data Exchange (ETDEWEB)

Mattera, Ch

1998-11-10

This thesis is concerned with Criticality-Safety studies related to the French Nuclear Fuel Cycle. We first describe the steps in the nuclear fuel cycle and the specific characteristics of these studies compared with those performed in Reactor Physics. In order to respond to the future requirements of the French Nuclear Program, we have developed a new package CRISTAL based on a recent cross sections library (CEA93) and the newest accurate codes (APOLLO2, MORET4, TRIPOLI4). The cristal system includes two calculations routes: a design route which will be used by French Industry (COGEMA/SGN) and a reference route.) To transfer this package to the French industry, we have elaborated calculation schemes for fissile solutions, dissolver media, transport casks and storage pools. Afterwards, these schemes have been used for the CRISTAL experimental validation. We have also contributed to the CRISTAL experimental database by reevaluating a French storage pool experiment: the CRISTO II experiment. This revaluation has been submitted to the OCDE working group in order that this experiment can be used by international criticality safety engineers to validate calculations methods. This work represents a large contribution to the recommendation of accurate calculation schemes and to the experimental validation of the CRISTAL package. These studies came up to the French Industry expectations. (author) 70 refs.

Challenges for the nuclear safety of the deregulation of electricity markets; Defis pour la surete nucleaire de la dereglementation des marches de l'electricite

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

Eurosafe 2000 was organised around two round tables on the first day and four seminars on the second day. The first round table dealt with general aspects of deregulation including the economic constraints and the special challenges arising during transition from regulated to deregulated structures. The second round table focussed on technical and organisational safety issues which are directly or indirectly related to the changes introduced by deregulation. The four seminars hold in order to provide opportunities for comparing experiences and learning about recent activities of IPSN, GRS and their partners in the European Union and Eastern Europe: Seminar 1 (Nuclear installation safety, assessment and analysis): assessment of the flooding incident at the Blayais nuclear power plant; PSA data base, comparison of the French and German approach; assessment of the Balakovo fire probabilistic study and elaboration of a guide for reviewing fire PSA; comprehensive technical assessment of an advanced German PWR by PSA - objectives and main results; PSA approach for the safety assessment of low-power and shutdown states; correlation of initiating events with the PSA level-2 results; safety assessment for fission products tests in the Phebus reactor; use of NPP simulators for applied human factor studies; assessment of the 'deterministic realistic method' applied to large LOCA analysis; assessment of the feasibility of an improvement programme enabling operation of units 3 and 4 of Kozloduy nuclear power plant. Seminar 2 (nuclear installation safety, research): PHEBUS 2K project on severe accidents; current status of the COCOSYS development; fission product modeling in ASTEC; Euratom Framework Programme (FP) research in reactor safety: main achievements of FP- 4 (1994-1998), some preliminary results of FP-5 (1998-2002) and prospects for beyond 2002; development of coupled systems of 3D neutronics and fluid-dynamic system codes and their application for safety

Progress report: nuclear safety and radiation protection in France in 2005; Rapport annuel: la surete nucleaire et la radioprotection en France en 2005

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

The Asn (Nuclear safety authority) considers that 2005 was a satisfactory year in terms of nuclear safety and radiation protection. However, further progress can and must be made. 2005 was a year of great progress for the Asn as it consolidated its organisation and working methods, in accordance with the 2005-2007 strategic plan it set for itself. The Asn continued progress in the field of radiation protection has given rise to various new regulations to improve the legislative and regulatory framework in this area. 2005 was marked by significant progress in the process of harmonizing national nuclear safety policies Against a backdrop of the preparation of a bill on management of radioactive materials and waste, to be presented to Parliament in March 2006, 2005 was a year of important milestones. The Asn control activities encompass the following seven areas: development of general regulations for nuclear safety and radiation protection; management of individual authorization requests and receipt of declarations; inspection of nuclear activities; organisation of radiological surveillance of individuals and of the environment; preparation for management of emergency situations and implementation if necessary; contribution to public information on nuclear safety and radiation protection; determination of the French position within international community. Main topics in 2005: government bill on transparency and security in the nuclear field; the challenges and ambitions of the Asn; controlling exposure to radon; EPR Reactor Project Safety; working towards a law on radioactive waste in 2006; I.R.R.T.: an international audit of Asn in 2006; harmonization of nuclear safety in Europe; Chernobyl: what has been achieved over the past 20 years; informing the Public; internal authorizations. (N.C.)

Europe's progress towards joint regulation of nuclear safety; Le cheminement de l'Europe vers une reglementation commune sur la surete nucleaire

Energy Technology Data Exchange (ETDEWEB)

Hennenhofer, G. [surete des installations nucleaires et la radioprotection, Ministere de l' Environnement, de la Protection de la nature et de la securite nucleaire (BMU) (Germany)

2010-11-15

Following the end of the Second World War, there was great hope for the use of nuclear energy for peaceful applications. In the beginning, the different approaches adopted by East and West led to the design of different types of reactors, with priority being given to rapid development of the reactor fleet. Cooperation between safety regulators only came about very gradually. The Chernobyl disaster was in this respect the trigger event, as it clearly showed that the effects of nuclear events do not stop at borders and that collaboration by the safety regulators in this field was essential. Texts such as the Convention on Nuclear Safety, requiring the creation of a regulatory body independent of economic interests, the other work done by IAEA on the issue of nuclear safety and, within the European context, the creation of WENRA, are all milestones along the path to close cooperation. The recently adopted European directive on the safety of nuclear installations is the natural successor to these achievements. The road to a common European vision of nuclear safety is now mapped out. Germany will be joining this movement and making its own contribution. (author)

Long-term behaviour of radioactive nuclides in the environment

International Nuclear Information System (INIS)

Brechignac, F.; Moberg, L.; Suomela, M.

1999-01-01

Report of recent advances in Europe, regarding the long-term development of radioactive nuclides in the environment. The corresponding scientific findings from three projects - Peace, Landscape and Epora (involving 18 European laboratories) - have been collected together. These projects were managed by the IPSN for the European Commission (DG XII) in the framework of the programme 'Surete de la fission nucleaire' (Nuclear fission safety programme). (author)

Hearing of Mrs Marie-Pierre Comets and Mr Marc Sanson, commissioners of the Nuclear Safety Authority (ASN), as well as Mrs Marie-Claude Dupuis, general manager of the National Agency for the management of radioactive wastes (ANDRA), on the nuclear events in Cadarache

International Nuclear Information System (INIS)

2009-01-01

Representatives of the French Nuclear Safety Authority (ASN, Autorite de Surete Nucleaire) and of the French National Agency for the Management of Radioactive Wastes (ANDRA, Agence nationale pour la gestion des dechets radioactifs) answer questions about an incident which occurred in a workshop, where MOx fuel was produced and which is now being dismantled. It appeared that the amount of plutonium present in the gloveboxes has been largely under-assessed: 8 kg were expected, 22 kg of plutonium have already been recovered, and finally 39 kg might be recovered by the end the dismantling operations. Other issues are addressed like the ANDRA's projects of radioactive material geological storage, their technical and institutional aspects, and then again about the late declaration of the Cadarache incident

IPSN activity report 1999; Rapport d'activite de l'IPSN 1999

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-07-01

The ''Institut de Protection et de Surete Nucleaire'' (IPSN), carries out researches and expert studies needed to manage nuclear risks and their consequences on people and environment. These activities cover the installation safety, the radioactive matter transport, the public health and environmental control, the nuclear matters safety and control and the crisis situation management. The IPSN have got also a mission of public information and participates to international actions in the domain of scientific researches or expert's report. This annual report presents the highlights of the year 1999, information on staff, budgets and geographical situation. Then technical and scientific papers gathers the activities of the year covered by the IPSN: the ''Free Tribune'', installations and radioactive wastes safety, crisis and nuclear matter management, public health and environment control, international cooperation. (A.L.B.)

Activity report 1998; Rapport d'activite 1998

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-07-01

The ''Institut de Protection et de Surete Nucleaire'' (IPSN), carries out researches and expert studies needed to manage nuclear risks and their consequences on people and environment. These activities cover the installation safety, the radioactive matter transport, the public health and environmental control, the nuclear matters safety and control and the crisis situation management. The IPSN have got also a mission of public information and participates to international actions in the domain of scientific researches or expert's report. This annual report presents the highlights of the year 1998, information on staff, budgets and geographical situation. Then technical and scientific papers gathers the activities of the year covered by the IPSN: the ''Free Tribune'', installations and radioactive wastes safety, crisis and nuclear matter management, public health and environment control, international cooperation. (A.L.B.)

Activity report 1998

International Nuclear Information System (INIS)

1998-01-01

The ''Institut de Protection et de Surete Nucleaire'' (IPSN), carries out researches and expert studies needed to manage nuclear risks and their consequences on people and environment. These activities cover the installation safety, the radioactive matter transport, the public health and environmental control, the nuclear matters safety and control and the crisis situation management. The IPSN have got also a mission of public information and participates to international actions in the domain of scientific researches or expert's report. This annual report presents the highlights of the year 1998, information on staff, budgets and geographical situation. Then technical and scientific papers gathers the activities of the year covered by the IPSN: the ''Free Tribune'', installations and radioactive wastes safety, crisis and nuclear matter management, public health and environment control, international cooperation. (A.L.B.)

IPSN activity report 1999

International Nuclear Information System (INIS)

1999-01-01

The ''Institut de Protection et de Surete Nucleaire'' (IPSN), carries out researches and expert studies needed to manage nuclear risks and their consequences on people and environment. These activities cover the installation safety, the radioactive matter transport, the public health and environmental control, the nuclear matters safety and control and the crisis situation management. The IPSN have got also a mission of public information and participates to international actions in the domain of scientific researches or expert's report. This annual report presents the highlights of the year 1999, information on staff, budgets and geographical situation. Then technical and scientific papers gathers the activities of the year covered by the IPSN: the ''Free Tribune'', installations and radioactive wastes safety, crisis and nuclear matter management, public health and environment control, international cooperation. (A.L.B.)

Improving safety culture through the health and safety organization: a case study.

Science.gov (United States)

Nielsen, Kent J

2014-02-01

International research indicates that internal health and safety organizations (HSO) and health and safety committees (HSC) do not have the intended impact on companies' safety performance. The aim of this case study at an industrial plant was to test whether the HSO can improve company safety culture by creating more and better safety-related interactions both within the HSO and between HSO members and the shop-floor. A quasi-experimental single case study design based on action research with both quantitative and qualitative measures was used. Based on baseline mapping of safety culture and the efficiency of the HSO three developmental processes were started aimed at the HSC, the whole HSO, and the safety representatives, respectively. Results at follow-up indicated a marked improvement in HSO performance, interaction patterns concerning safety, safety culture indicators, and a changed trend in injury rates. These improvements are interpreted as cultural change because an organizational double-loop learning process leading to modification of the basic assumptions could be identified. The study provides evidence that the HSO can improve company safety culture by focusing on safety-related interactions. © 2013. Published by Elsevier Ltd and National Safety Council.

Study on the KALIMER safety approach

International Nuclear Information System (INIS)

Kim, Eui Kwang; Han, Do Hee; Kim, Young Cheol.

1997-01-01

This study describes KALIMER's safety approach, how to establish the safety criteria and temperature limit, how to define safety evaluation events, and some safety research and development needs items. It is recommended that the KALIMER's approach to safety use seven levels of safety design and a defense-in-depth design approach with particular emphasis on inherent passive features. In order to establish as set DBEs for KALIMER safety evaluation, the procedure is explained how to define safety evaluation events. Final selection is to be determined later with the final establishment of design concepts. On the basis of preliminary studies and evaluation of the plant safety related areas, the KALIMER and PRISM have following three main difference that may require special research and development for KALIMER. (author). 7 refs., 6 tabs., 6 figs

Activity report 1998; Rapport d'activite 1998

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-07-01

The ''Institut de Protection et de Surete Nucleaire'' (IPSN), carries out researches and expert studies needed to manage nuclear risks and their consequences on people and environment. These activities cover the installation safety, the radioactive matter transport, the public health and environmental control, the nuclear matters safety and control and the crisis situation management. The IPSN have got also a mission of public information and participates to international actions in the domain of scientific researches or expert's report. This annual report presents the highlights of the year 1998, information on staff, budgets and geographical situation. Then technical and scientific papers gathers the activities of the year covered by the IPSN: the ''Free Tribune'', installations and radioactive wastes safety, crisis and nuclear matter management, public health and environment control, international cooperation. (A.L.B.)

IPSN activity report 1999; Rapport d'activite de l'IPSN 1999

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-07-01

The ''Institut de Protection et de Surete Nucleaire'' (IPSN), carries out researches and expert studies needed to manage nuclear risks and their consequences on people and environment. These activities cover the installation safety, the radioactive matter transport, the public health and environmental control, the nuclear matters safety and control and the crisis situation management. The IPSN have got also a mission of public information and participates to international actions in the domain of scientific researches or expert's report. This annual report presents the highlights of the year 1999, information on staff, budgets and geographical situation. Then technical and scientific papers gathers the activities of the year covered by the IPSN: the ''Free Tribune'', installations and radioactive wastes safety, crisis and nuclear matter management, public health and environment control, international cooperation. (A.L.B.)

Safety report concerning Melusine (after power increase to 4 MW). Descriptive part. Volumes 1 and 2; Rapport de surete de ''melusine'' (apres augmentation de puissance a 4 MW). Partie descriptive. Tomes 1 et 2

Energy Technology Data Exchange (ETDEWEB)

Baas, C; Delcroix, V; Jacquemain, M; Marouby, R; Meunier, C; De Robien, E; Rossillon, F [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

1967-03-01

Construction of Melusine was started in January 1957, It first diverged on July 1, 1958. It operated at: 1 MW from March 1959; 1.4 MW from April 1960; 2 MW from September 1961; 4 MW from December 1965. Various modifications have been made since the reactor was built. They concern: - the addition of a hot cell. - the effluents: 2 reservoirs of 15 m{sup 3} for liquid waste have been installed. The resin regeneration equipment has been completely modified. - the building: offices have been added - experimental zones have been set up in the hall - the electrical supply. - the cooling and purification circuits (installation of a second exchanger, replacement of the primary pumps, creation of a hot layer, etc... ). - the fuel elements (at the moment of the MTR type enriched to 90 per cent). - the swimming-pool (which has been partially equipped with a stainless steel coating). - the core (placing of 'stools', of a diving-board, etc...). - the ventilation: the hall has been de-pressurized during normal working in the event of an accident, the hall can be isolated and a safety circuit can be started up. A chimney has been installed. - the hall (which has been strengthened and sealed more effectively). - the control electronics (modification of the principle, and which are now entirely transistorized). So many changes have been made that the reactor now bears only a slight resemblance to the initial model. It has appeared necessary to make a brief review of these improvements in order to be able to judge more effectively the installations present safety characteristics; these latter are furthermore fairly well known as a result of the experiments carried out not only by the Thermal Transfer Service in Grenoble but also at Cadarache (Cabri) and Toulon (the work of Mr. PASCOUET). (authors) [French] MELUSINE a ete construite a partir de janvier 1957. Sa premiere divergence a eu lieu le 1er juillet 1958. Elle a fonctionne a: 1 MW a partir de mars 1959; 1,4 MW a partir d

Safety precautions in atomic pile control (1962); Securite dans le controle des piles atomiques (1962)

Energy Technology Data Exchange (ETDEWEB)

Furet, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1962-07-01

We have been led to study the problem of safety in atomic pile control as a result of our participation on the one hand in the planning of C.E.A. atomic piles, and on the other hand in the pile safety sub omission considering atomic pile safety of operational or planned C.E.A. piles. We have thus had to consider the wishes occurring in piles during their operation and also their behaviour in the dynamic state The present work deals mainly with the importance of intrinsic safety devices, with the influence of reactivity variations on the power fluctuations during accidental operation, and with the development of robust and reliable safety appliances. The starting p accident has been especially studied both for low-flux piles where a compromise is necessary between the response time of the safety appliances and the statistical fluctuations and for high lux piles where xenon poisoning has an effect on the lower limit of the velocity of reactivity liberation. The desirability has been stressed of automation as a safety factor in atomic pile control. The details required for an understanding of the diagrams of the apparatus are given. (author) [French] Nous avons aborde le probleme de la securite dans le controle des piles atomiques a la suite de notre participation d'une part aux avant rojets de piles atomiques du CE.A. et d'autre part a l'examen au sein de la sous ommission de surete des piles, de la securite des piles du CE.A. en fonctionnement ou en projet. Nous avons ete amenes a nous interesser alors aux risques encourus par les piles pendant leur fonctionnement et par la meme a leur comportement en regime dynamique. Ce travail traite principalement de l'importance des securites intrinseques, de l'influence des variations de reactivite sur les evolutions de puissance en regime d'accident et du developpement d'appareillages de securite robustes et de fonctionnement tres sur. L'accident de demarrage a ete particulierement developpe aussi bien pour les piles a bas

Safety precautions in atomic pile control (1962); Securite dans le controle des piles atomiques (1962)

Energy Technology Data Exchange (ETDEWEB)

Furet, J. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1962-07-01

We have been led to study the problem of safety in atomic pile control as a result of our participation on the one hand in the planning of C.E.A. atomic piles, and on the other hand in the pile safety sub omission considering atomic pile safety of operational or planned C.E.A. piles. We have thus had to consider the wishes occurring in piles during their operation and also their behaviour in the dynamic state The present work deals mainly with the importance of intrinsic safety devices, with the influence of reactivity variations on the power fluctuations during accidental operation, and with the development of robust and reliable safety appliances. The starting p accident has been especially studied both for low-flux piles where a compromise is necessary between the response time of the safety appliances and the statistical fluctuations and for high lux piles where xenon poisoning has an effect on the lower limit of the velocity of reactivity liberation. The desirability has been stressed of automation as a safety factor in atomic pile control. The details required for an understanding of the diagrams of the apparatus are given. (author) [French] Nous avons aborde le probleme de la securite dans le controle des piles atomiques a la suite de notre participation d'une part aux avant rojets de piles atomiques du CE.A. et d'autre part a l'examen au sein de la sous ommission de surete des piles, de la securite des piles du CE.A. en fonctionnement ou en projet. Nous avons ete amenes a nous interesser alors aux risques encourus par les piles pendant leur fonctionnement et par la meme a leur comportement en regime dynamique. Ce travail traite principalement de l'importance des securites intrinseques, de l'influence des variations de reactivite sur les evolutions de puissance en regime d'accident et du developpement d'appareillages de securite robustes et de fonctionnement tres sur. L'accident de demarrage a ete particulierement

Nuclear safety and radiation protection report of the Chooz nuclear facilities - 2010; Rapport sur la surete nucleaire et la radioprotection des installations nucleaires de Chooz - 2010

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-06-15

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Chooz nuclear power plant (Ardennes (FR)): 2 PWR reactors in operation (Chooz B, INB 139 and 144) and one partially dismantled PWR reactor (Chooz A, INB 163). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Flamanville nuclear facilities - 2010; Rapport sur la surete nucleaire et la radioprotection des installations nucleaires de Flamanville - 2010

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-06-15

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Flamanville nuclear power plant (Manche (FR)): 2 PWR reactors in operation (INB 108 and 109), and 1 PWR under construction (Flamanville 3, INB 167). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, water consumption and waste management at Flamanville 3 construction site) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nordic studies in reactor safety

International Nuclear Information System (INIS)

Pershagen, N.

1993-01-01

The Nordic Nuclear Safety Research Programme SIK programme in reactor safety is part of a major joint Nordic research effort in nuclear safety. The report summarizes the achievements of the SIK programme, which was carried out during 1990-1993 in collaboration between Nordic nuclear utilities, safety authorities, and research institutes. Three main projects were successfully completed dealing with: 1) development and application of a living PSA concept for monitoring the risk of core damage, and of safety indicators for early warning of possible safety problems; 2) review and intercomparison of severe accident codes, case studies of potential core melt accidents in nordic reactors, development of chemical models for the MAAP code, and outline of a system for computerized accident management support; 3) compilation of information about design and safety features of neighbouring reactors in Germany, Lithuania and Russia, and for naval reactors and nuclear submarines. The report reviews the state-of-the-art in each subject matter as an introduction to the individual project summaries. The main findings of each project are highlighted. The report also contains an overview of reactor safety research in the Nordic countries and a summary of fundamental reactor safety principles. (au) (69 refs.)

Complementary safety assessment assessment of nuclear facilities - Tricastin facility - AREVA; Evaluation complementaire de la surete des installations nucleaires de base - Site du Tricastin - AREVA

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-01

This complementary safety assessment analyses the robustness of the Areva part of the Tricastin nuclear site to extreme situations such as those that led to the Fukushima accident. This study includes the following facilities: Areva NC Pierrelatte, EURODIF production, Comurhex Pierrelatte, Georges Besse II plant and Socatri. Robustness is the ability for the plant to withstand events beyond which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accidental sequence. Moreover, safety is not only a matter of design or engineered systems but also a matter of organizing: task organization (including subcontracting) as well as the setting of emergency plans or the inventory of nuclear materials are taken into consideration in this assessment. This report is divided into 10 main chapters: 1) the feedback experience of the Fukushima accident; 2) description of the site and its surroundings; 3) featuring of the site's activities and installations; 4) accidental sequences; 5) protection from earthquakes; 6) protection from floods; 7) protection from other extreme natural disasters; 8) the loss of electrical power and of the heat sink; 9) the management of severe accidents; and 10) subcontracting policy. This analysis has identified 5 main measures to be taken to limit the risks linked to natural disasters: -) continuing the program for replacing the current conversion plant and the enrichment plant; -) renewing the storage of hydrofluoric acid at the de-fluorination workshop; -) assessing the seismic behaviour of some parts of the de-fluorination workshop and of the fluorine fabrication workshop; -) improving the availability of warning and information means in case of emergency; and -) improving the means to mitigate accidental gaseous releases. (A.C.)

The European nuclear safety and radiation protection area: steps and prospects; L'Europe de la surete nucleaire et de la radioprotection: grandes etapes et perspectives

Energy Technology Data Exchange (ETDEWEB)

Gillet, G. [Autorite de Surete Nucleaire, Dir. des relations internationales 75 - Paris (France)

2010-11-15

Launched with enthusiasm and determination in 1957, The European Atomic Energy Community (EAEC - EURATOM), which aimed to promote the development of a 'powerful nuclear industry' in Europe, has not ultimately fulfilled the wishes of its founding fathers. Rapidly, and on a topic as strategic as the peaceful use of the atom, national reflexes prevailed. The Chernobyl disaster, in 1986, also substantially slowed down the use of nuclear energy in Europe. Nuclear safety and radiation protection have followed two different paths. Backed by Chapter III of the EURATOM treaty, over time the EAEC has developed a substantial legislative corpus on radiation protection. Meanwhile, and strange as it may seem, nuclear safety has remained the poor relation, on the grounds that the treaty does not grant EURATOM competence in the area. It is true that legislation was adopted in reaction to Chernobyl, but for a long time there was no specific regulation of nuclear safety in the EU. The European nuclear safety and radiation protection area owes its construction to Community mechanisms as well as to informal initiatives by safety authorities. Today, more than ever, this centre provides consistency, an overall balance which should both strengthen it and impose it as an international reference. Progress can now be expected on waste management, radiation protection and the safety objectives of new reactors. (author)

Measuring Safety Culture on Ships Using Safety Climate: A Study among Indian Officers

Directory of Open Access Journals (Sweden)

Yogendra Bhattacharya

2015-12-01

Full Text Available Workplace safety continues to be an area of concern in the maritime industry due to the international nature of the operations. The effectiveness of extensive legislation to manage shipboard safety remains in doubt. The focus must therefore shift towards the human element - seafarers and their perceptions of safety. The study aims to understand the alignment that exists between safety culture and safety climate on board ships as perceived by seafarers. The underlying factors of safety climate were identified using factor analysis which isolated seven factors - Support on Safety, Organizational Support, Resource Availability, Work Environment, Job Demands, ‘Just’ Culture, and Safety Compliance. The perception of safety level of seafarers was found to be low indicating the existence of misalignments between safety culture values and the actual safety climate. The study also reveals that the safety perceptions of officers employed directly by ship owners and those by managers do not differ significantly, nor do they differ between senior and junior officers. A shift in perspective towards how seafarers themselves feel towards safety might provide more effective solutions – instead of relying on regulations - and indeed aid in reducing incidents on board. This paper details practical suggestions on how to identify the factors that contribute towards a better safety climate on board ships.

The evaluation of the nuclear facilities safety at the CEA from 1999 to 2001; Le bilan de la surete des installations nucleaires du CEA du 1999 a 2001

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-11-01

The aim of this document is the presentation of an evaluation of the problems and the safety methods in the concerned period. The first chapter presents the nuclear safety in the CEA. The second chapter is devoted to the organization and the quality for the safety: liabilities, audits, relations with the safety authorities and with the public. The chapters three and four deal respectively with the methodological and technical abilities supporting the exploitation teams and with the nuclear safety projects. The last chapter presents the experiments and events from 1999 to 2001. (A.L.B.)

Safety guidebook relative to the disposal of radioactive wastes in deep geologic formation; Guide de surete relatif au stockage definitif des dechets radioactifs en formation geologique profonde

Energy Technology Data Exchange (ETDEWEB)

NONE

2008-07-01

The French nuclear safety authority (ASN) initiated in 2003 a revision process of the objectives to be considered during the research and work steps of the implementation of a radioactive waste storage facility in deep geologic formations. The purpose of this document is to define the safety objectives that have to be retained at each step of this implementation, from the site characterization to the closure of the facility. This update takes into account the works carried out by the ANDRA (French national agency of radioactive wastes) in the framework of the law from December 30, 1991, and the advices of the permanent experts group about these works. It takes also into consideration the international research works in this domain and the choices defined in the program law no 2006-739 from June 28, 2006 relative to the sustainable management of radioactive materials and wastes. The main modifications concern: the notion of reversibility, the definition of the safety functions of disposal components, the safety goals and the design principles assigned to waste packages, the control of nuclear materials and the monitoring objectives of the facility. The documents treats of the following points: 1 - the objectives of public health and environment protection; 2 - the safety principles and the safety-related design bases of the facility; and 3 - the method used for demonstrating the disposal safety. (J.S.)

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

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

Railway safety climate: a study on organizational development.

Science.gov (United States)

Cheng, Yung-Hsiang

2017-09-07

The safety climate of an organization is considered a leading indicator of potential risk for railway organizations. This study adopts the perceptual measurement-individual attribute approach to investigate the safety climate of a railway organization. The railway safety climate attributes are evaluated from the perspective of railway system staff. We identify four safety climate dimensions from exploratory factor analysis, namely safety communication, safety training, safety management and subjectively evaluated safety performance. Analytical results indicate that the safety climate differs at vertical and horizontal organizational levels. This study contributes to the literature by providing empirical evidence of the multilevel safety climate in a railway organization, presents possible causes of the differences under various cultural contexts and differentiates between safety climate scales for diverse workgroups within the railway organization. This information can be used to improve the safety sustainability of railway organizations and to conduct safety supervisions for the government.

French statutory approach of the evaluation of the safety level of old nuclear divisions; Approche reglementaire francaise de l`appreciation du niveau de surete des tranches anciennes

Energy Technology Data Exchange (ETDEWEB)

Delage, M

1994-06-01

The legal French procedures include three steps which have to be followed during the exam of the safety in nuclear plants (creation authorization, loading authorization, actual running of the plant). After listing the different types of evaluation of safety in fraction of plants, this report presents the main themes encountered during the safety assessment: state of the reactor, maintenance, tracking of the incidents, personnel training, radioprotection, radioactive releases. The Fessenheim and Bugey list of reevaluation themes is also given. (TEC).

Safety and man in light of the analysis of major technical accidents

International Nuclear Information System (INIS)

Carnino, A.

1990-01-01

Up to the seventies, it was not easy to admit human failure as a cause of industrial accidents. Man was considered as reliable. With the perfection of materials, technical systems and industrial processes though, man has become the weakest link in the chain of technical events. He is and stays a remarkably reliable being, with a roughly estimated average failure quota of 1:1000 manipulations. If the hypothetical risk should be kept very low, this value can become a problem. Instead of judging a mistake as a punishable crime, as the present tendency will have it, a more differentiated, systematical approach is called for. By means of an analysis of four major accidents - Chernobyl, Three Mile Island, Challenger and Bhopal - interesting parallels between the causes of such accidents can be found. Human failure, e.g. of a surgeon, is in most cases, the direct cause of an accident. A whole series of further causes, which can be assigned to different areas of influence but are usually interdependent, also play a role. While the human factor must be viewed as more or less predetermined, far reaching improvements can be made to reduce the risk of accident. Today, thanks to modern technology and new findings, it is possible to practically neutralize human error. This creates more costs and necessitates giving up short term production maximization. It also requires the willingness to give safety absolute priority. The name 'culture de surete' (safety culture) is used to describe this concept. Surprising similarities between the causes of the four mentioned major accidents were discovered. Certain circumstances, such as the time of day, played a role. The concept of a plant, resp. technical process has an essential influence, as well as company policy (importance of safety, preparation of emergency procedures, training, maintenance, company rules) and management (evaluation and realization of foreign and the company's own operation experiences and error alarms). (author) 7

Position adopted by the government about the safety options of the EPR reactor project; Prise de position du gouvernement concernant les options de surete du projet de reacteur EPR

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-10-01

On September 28, 2004, on behalf of the French ministers in charge of nuclear safety, the general director of nuclear safety and radiation protection addressed to the president of Electricite de France (EdF) a letter presenting the government's position about the safety options of the EPR (European Pressurized Reactor) project. On the basis of the examination carried out by the nuclear safety authority (ASN) and by the permanent group of reactor experts, the government has considered these options as satisfactory with respect to the safety improvement objectives. Therefore, the government requested EdF to comply with these technical rules for any future reactor development. This dossier includes: the letter of the government, the technical directives for the design and construction of the next generation of PWR-type reactors, the technical rules relative to the design of the main primary and secondary coolant circuits of PWR-type reactors, and the technical file about the safety of the EPR project reprinted from the 2003 report of nuclear safety and radiation protection authority. (J.S.)

Criticality accident studies and research performed in the Valduc criticality laboratory, France

International Nuclear Information System (INIS)

Barbry, F.; Fouillaud, P.

2001-01-01

In 1967, the IPSN (Institut de Protection et de Surete Nucleaire - Nuclear Protection and Safety Institute) started studies and research in France on criticality accidents, with the objective of improving knowledge and modelling of accidents in order to limit consequences to the public, the environment and installations. The criticality accident is accompanied by an intense emission of neutronic and gamma radiation and releases of radioactive products in the form of gas and aerosols, generating irradiation and contamination risks. The main objectives of the studies carried out, particularly using the CRAC installation and the SILENE reactor at Valduc (France), were to model the physics of criticality accidents, to estimate the risks of irradiation and radioactive releases, to elaborate an accident detection system and to provide information for intervention plans. This document summarizes the state of knowledge in the various fields mentioned above. The results of experiments carried out in the Valduc criticality laboratory are used internationally as reference data for the qualification of calculation codes and the assessment of the consequences of a criticality accident. The SILENE installation, that reproduces the various conditions encountered during a criticality accident, is also a unique international research tool for studies and training on those matters. (author)

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

International Nuclear Information System (INIS)

Hasegawa, Naoko; Takano, Kenichi; Hirose, Ayako

2001-01-01

In a report after the Chernobyl accident, the International Atomic Energy Agency indicated the definition and the importance of safety culture and the ideal organizational state where safety culture pervades. However, the report did not mention practical approaches to enhance safety culture. In Japan, although there had been investigations that clarified the consciousness of employees and the organizational climate in the nuclear power and railway industries, organizational factors that clarified the level of organization safety and practical methods that spread safety culture in an organization had not been studied. The Central Research Institute of the Electric Power Industry conducted surveys of organizational culture for the construction, chemical, and manufacturing industries. The aim of our study was to clarify the organizational factors that influence safety in an organization expressed in employee safety consciousness, commitment to safety activities, rate of accidents, etc. If these areas were clarified, the level of organization safety might be evaluated, and practical ways could be suggested to enhance the safety culture. Consequently, a series of investigations was conducted to clarify relationships among organizational climate, employee consciousness, safety management and activities, and rate of accidents. The questionnaire surveys were conducted in 1998-1999. The subjects were (a) managers of the safety management sections in the head offices of the construction, chemical, and manufacturing industries; (b) responsible persons in factories of the chemical and manufacturing industries; and (c) general workers in factories of the chemical and manufacturing industries. The number of collected data was (a) managers in the head office: 48 from the construction industry and 58 from the chemical and manufacturing industries, (b) responsible persons in factories: 567, and (c) general workers: from 29 factories. Items in the questionnaires were selected from

To dimension safety valves. Probabilist study

International Nuclear Information System (INIS)

Noel, Robert; Couvreur, Denis

1982-01-01

The gauge of safety valves of a steam pressure apparatus is usually determined according to an operating situation envelope which it is admitted covers all that can happen in reality. For the safety of the dryer-superheaters of turbines in nuclear power stations, Electricite de France and Alsthom-Atlantique made a reliability study; its method is exposed and the results are discussed. Such a study is heavy going and complex, but in return it permits a better quantitative understanding of the various dimension and operating parameters of an installation which condition its safety. It is therefore a source of progress [fr

Model quality and safety studies

DEFF Research Database (Denmark)

Petersen, K.E.

1997-01-01

The paper describes the EC initiative on model quality assessment and emphasizes some of the problems encountered in the selection of data from field tests used in the evaluation process. Further, it discusses the impact of model uncertainties in safety studies of industrial plants. The model...... that most of these have never been through a procedure of evaluation, but nonetheless are used to assist in making decisions that may directly affect the safety of the public and the environment. As a major funder of European research on major industrial hazards, DGXII is conscious of the importance......-tain model is appropriate for use in solving a given problem. Further, the findings from the REDIPHEM project related to dense gas dispersion will be highlighted. Finally, the paper will discuss the need for model quality assessment in safety studies....

Scientific and technical report, 2000 of the IPSN

International Nuclear Information System (INIS)

2001-01-01

IPSN (Institut de Protection et de Surete Nucleaire) is responsible for dealing with all aspects in the evaluation of safety of nuclear installations involving the human factors. To achieve its objectives, it conducts its own research and development activities on these themes. This report highlights the most significant scientific and technical achievements of the Institut in 2000. Twenty eight reports are presented, grouped in eight sessions, each ones opened by a review paper: the reactors safety, the installations safety, the radioactive materials and transport safety, the public health, the environment protection, the radioactive wastes safety, the crisis management and the IPSN installations. The international research program Phebus PF is detailed, technical progresses concerning the steam generators nondestructive testing or the impact of automation on operator performance are also presented. One session deals with the criticality studies and risk assessment. The control and surveillance of nuclear materials form the subject of research programs and experiments as well as the transport safety. Concerning the public and environment protection inspections, epidemiological studies, radionuclides transportation and radio-contaminant behavior are reported. In the domain of the radioactive wastes safety, the deep underground storage and the model MELODIE are presented. Examples of accidents or the INEX2 exercise are also discussed. (A.L.B.)

Scientific and technical report, 2000 of the IPSN; Rapport scientifique et technique 2000 de l'IPSN

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

IPSN (Institut de Protection et de Surete Nucleaire) is responsible for dealing with all aspects in the evaluation of safety of nuclear installations involving the human factors. To achieve its objectives, it conducts its own research and development activities on these themes. This report highlights the most significant scientific and technical achievements of the Institut in 2000. Twenty eight reports are presented, grouped in eight sessions, each ones opened by a review paper: the reactors safety, the installations safety, the radioactive materials and transport safety, the public health, the environment protection, the radioactive wastes safety, the crisis management and the IPSN installations. The international research program Phebus PF is detailed, technical progresses concerning the steam generators nondestructive testing or the impact of automation on operator performance are also presented. One session deals with the criticality studies and risk assessment. The control and surveillance of nuclear materials form the subject of research programs and experiments as well as the transport safety. Concerning the public and environment protection inspections, epidemiological studies, radionuclides transportation and radio-contaminant behavior are reported. In the domain of the radioactive wastes safety, the deep underground storage and the model MELODIE are presented. Examples of accidents or the INEX2 exercise are also discussed. (A.L.B.)

Scientific and technical report, 2000 of the IPSN; Rapport scientifique et technique 2000 de l'IPSN

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

IPSN (Institut de Protection et de Surete Nucleaire) is responsible for dealing with all aspects in the evaluation of safety of nuclear installations involving the human factors. To achieve its objectives, it conducts its own research and development activities on these themes. This report highlights the most significant scientific and technical achievements of the Institut in 2000. Twenty eight reports are presented, grouped in eight sessions, each ones opened by a review paper: the reactors safety, the installations safety, the radioactive materials and transport safety, the public health, the environment protection, the radioactive wastes safety, the crisis management and the IPSN installations. The international research program Phebus PF is detailed, technical progresses concerning the steam generators nondestructive testing or the impact of automation on operator performance are also presented. One session deals with the criticality studies and risk assessment. The control and surveillance of nuclear materials form the subject of research programs and experiments as well as the transport safety. Concerning the public and environment protection inspections, epidemiological studies, radionuclides transportation and radio-contaminant behavior are reported. In the domain of the radioactive wastes safety, the deep underground storage and the model MELODIE are presented. Examples of accidents or the INEX2 exercise are also discussed. (A.L.B.)

Very high temperature measurements: Applications to nuclear reactor safety tests; Mesures des tres hautes temperatures: Applications a des essais de surete des reacteurs nucleaires

Energy Technology Data Exchange (ETDEWEB)

Parga, Clemente-Jose

2013-09-27

This PhD dissertation focuses on the improvement of very high temperature thermometry (1100 deg. C to 2480 deg. C), with special emphasis on the application to the field of nuclear reactor safety and severe accident research. Two main projects were undertaken to achieve this objective: - The development, testing and transposition of high-temperature fixed point (HTFP) metal-carbon eutectic cells, from metrology laboratory precision (±0.001 deg. C) to applied research with a reasonable degradation of uncertainties (±3-5 deg. C). - The corrosion study and metallurgical characterization of Type-C thermocouple (service temp. 2300 deg. C) prospective sheath material was undertaken to extend the survivability of TCs used for molten metallic/oxide corium thermometry (below 2000 deg. C)

Safety report concerning Melusine (after power increase to 4 MW). Descriptive part. Volumes 1 and 2; Rapport de surete de ''melusine'' (apres augmentation de puissance a 4 MW). Partie descriptive. Tomes 1 et 2

Energy Technology Data Exchange (ETDEWEB)

Baas, C.; Delcroix, V.; Jacquemain, M.; Marouby, R.; Meunier, C.; De Robien, E.; Rossillon, F. [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

1967-03-01

Construction of Melusine was started in January 1957, It first diverged on July 1, 1958. It operated at: 1 MW from March 1959; 1.4 MW from April 1960; 2 MW from September 1961; 4 MW from December 1965. Various modifications have been made since the reactor was built. They concern: - the addition of a hot cell. - the effluents: 2 reservoirs of 15 m{sup 3} for liquid waste have been installed. The resin regeneration equipment has been completely modified. - the building: offices have been added - experimental zones have been set up in the hall - the electrical supply. - the cooling and purification circuits (installation of a second exchanger, replacement of the primary pumps, creation of a hot layer, etc... ). - the fuel elements (at the moment of the MTR type enriched to 90 per cent). - the swimming-pool (which has been partially equipped with a stainless steel coating). - the core (placing of 'stools', of a diving-board, etc...). - the ventilation: the hall has been de-pressurized during normal working in the event of an accident, the hall can be isolated and a safety circuit can be started up. A chimney has been installed. - the hall (which has been strengthened and sealed more effectively). - the control electronics (modification of the principle, and which are now entirely transistorized). So many changes have been made that the reactor now bears only a slight resemblance to the initial model. It has appeared necessary to make a brief review of these improvements in order to be able to judge more effectively the installations present safety characteristics; these latter are furthermore fairly well known as a result of the experiments carried out not only by the Thermal Transfer Service in Grenoble but also at Cadarache (Cabri) and Toulon (the work of Mr. PASCOUET). (authors) [French] MELUSINE a ete construite a partir de janvier 1957. Sa premiere divergence a eu lieu le 1er juillet 1958. Elle a fonctionne a: 1 MW a partir de mars 1959; 1,4 MW a partir

77 FR 27776 - Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety...

Science.gov (United States)

2012-05-11

... Occupational Health Study Section (SOHSS), National Institute for Occupational Safety and Health (NIOSH) In... Services Office, CDC, pursuant to Public Law 92-463. Purpose: The Safety and Occupational Health Study... standard grants review and funding cycles pertaining to research issues in occupational safety and health...

76 FR 18220 - Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety...

Science.gov (United States)

2011-04-01

... Occupational Health Study Section (SOHSS), National Institute for Occupational Safety and Health (NIOSH) In... Services Office, CDC, pursuant to Public Law 92-463. Purpose: The Safety and Occupational Health Study... standard grants review and funding cycles pertaining to research issues in occupational safety and health...

Fusion reactor safety studies, FY 1977

International Nuclear Information System (INIS)

Darby, J.B. Jr.

1978-04-01

This report reviews the technical progress in the fusion reactor safety studies performed during FY 1977 in the Fusion Power Program at the Argonne National Laboratory. The subjects reported on include safety considerations of the vacuum vessel and first-wall design for the ANL/EPR, the thermal responses of a tokamak reactor first wall, the vacuum wall electrical resistive requirements in relationship to magnet safety, and a major effort is reported on considerations and experiments on air detritiation

75 FR 26266 - Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety...

Science.gov (United States)

2010-05-11

... Occupational Health Study Section (SOHSS), National Institute for Occupational Safety and Health (NIOSH) In...) Public Law 92-463. Purpose: The Safety and Occupational Health Study Section will review, discuss, and... cycles pertaining to research issues in occupational safety and health, and allied areas. It is the...

State of the art on the probabilistic safety assessment (P.S.A.); Etat de l'art sur les etudes probabilistes de surete (E.P.S.)

Energy Technology Data Exchange (ETDEWEB)

Devictor, N.; Bassi, A.; Saignes, P.; Bertrand, F

2008-07-01

The use of Probabilistic Safety Assessment (PSA) is internationally increasing as a means of assessing and improving the safety of nuclear and non-nuclear facilities. To support the development of a competence on Probabilistic Safety Assessment, a set of states of the art regarding these tools and their use has been made between 2001 and 2005, in particular on the following topics: - Definition of the PSA of level 1, 2 and 3; - Use of PSA in support to design and operation of nuclear plants (risk-informed applications); - Applications to Non Reactor Nuclear Facilities. The report compiled in a single document these states of the art in order to ensure a broader use; this work has been done in the frame of the Project 'Reliability and Safety of Nuclear Facility' of the Nuclear Development and Innovation Division of the Nuclear Energy Division. As some of these states of the art have been made in support to exchanges with international partners and were written in English, a section of this document is written in English. This work is now applied concretely in support to the design of 4. Generation nuclear systems as Sodium-cooled Fast Reactors and especially Gas-cooled Fast Reactor, that have been the subject of communications during the conferences ANS (Annual Meeting 2007), PSA'08, ICCAP'08 and in the journal Science and Technology of Nuclear Installations. (authors)

Experiments on the risk of sump plugging on French PWR

International Nuclear Information System (INIS)

Armand, Y.; Mattei, J.M.; Vicena, I.; Gubco, V.; Batalik, J.; Murani, J.; Davydov, M.; Melikhov, O.I.; Blinkov, V.N.

2003-01-01

The 'Institut de Radioprotection et de Surete Nucleaire' has decided to perform an experimental program of studies on the risk of sump plugging in a 900 MWe pressurized water reactor (PWR). A general overview of the literature has been conducted between October 1999 and November 2000, ending by the definition of an approach methodology and the written of technical specifications. The problem identified gave rise to an European call for tenders leading to four contracts signed in november 2001. Three contracts are managed by VUEZ (Slovakia), the last by EREC (Russia). The methodology and the facilities devoted to these studies are presented in this paper, the preliminary results observed are also presented. The objectives for 2003 to finalize the program and the safety assessment are presented. (authors)

Center for Maritime Safety and Health Studies

Data.gov (United States)

Federal Laboratory Consortium — Established in November 2015, the Center for Maritime Safety and Health Studies (CMSHS) promotes safety and health for all maritime workers, including those employed...

Study on Fusion Safety Infrastructure using ISAM

International Nuclear Information System (INIS)

Oh, Kyemin; Kang, Myungsuk; Heo, Gyunyoung; Kim, Hyoungchan

2013-01-01

The regulation of nuclear facilities have checked and managed safety throughout the entire process from design, construction, operation and decommissioning. Also, the same meaning as the regulatory requirements and design requirements, it will be important indicators for detailed design of K-DEMO. K-DEMO has many uncertainties because it is in conceptual design phase. Also, there is no reference material because demonstration scale fusion power plants were not operated yet in overseas. So, hazard that threaten the integrity of K-DEMO have to be defined preferentially to define regulatory or design requirements. This study proposed method that educe regulatory or design requirements and introduce web-based cloud infrastructure to perform renewal and sharing of information related with safety that is required in the study rapidly as a part of the R and D program funded by National Fusion Research Institute of Korea (NFRI). We have been performing QSR and PIRT in accordance with development of fusion DEMO plant, and preparing OPT, PSA and DPA for regulation requirements. This study introduces our recent research activities about ISAM for fusion and CCI built for expert and extant safety related information. Unlike fission, nuclear fusion's safety goal is non-evacuation of the public during an accident. To satisfy this goal not only various safety issues should be analyzed, but safety objectives, regulatory requirements, and design variables should also be established in detailed design phase. The web-based cloud infrastructure proposed in this paper will be able to offer input data of future studies and, it is expected to contribute on general and technical safety principles for national fusion power plant technology plan

The first symposium of Research Center for Radiation Safety, NIRS. Perspective of future studies of radiation safety

International Nuclear Information System (INIS)

Shimo, Michikuni

2002-03-01

This paper summarizes presentations given in the title symposium, held at the Conference Room of National Institute of Radiological Sciences (NIRS) on November 29 and 30, 2001. Contained are Introductory remarks: Basic presentations concerning exposure dose in man; Environmental levels of radiation and radioactivity, environmental radon level and exposure dose, and radiation levels in the specific environment (like in the aircraft): Special lecture (biological effects given by space environment) concerning various needs for studies of radiation safety; Requirement for open investigations, from the view of utilization, research and development of atomic energy, from the clinical aspect, and from the epidemiological aspect: Special lecture (safety in utilization of atomic energy and radiation-Activities of Nuclear Safety Commission of Japan) concerning present state and perspective of studies of radiation safety; Safety of radiation and studies of biological effects of radiation-perspective, and radiation protection and radiation safety studies: Studies in the Research Center for Radiation Safety; Summary of studies in the center, studies of the biological effects of neutron beam, carcinogenesis by radiation and living environmental factors-complicated effects, and studies of hereditary effects: Panel discussion (future direction of studies of radiation safety for the purpose of the center's direction): and concluding remarks. (N.I.)

Lessons learned from measuring safety culture: an Australian case study.

Science.gov (United States)

Allen, Suellen; Chiarella, Mary; Homer, Caroline S E

2010-10-01

adverse events in maternity care are relatively common but often avoidable. International patient safety strategies advocate measuring safety culture as a strategy to improve patient safety. Evidence suggests it is necessary to fully understand the safety culture of an organisation to make improvements to patient safety. this paper reports a case study examining the safety culture in one maternity service in Australia and considers the benefits of using surveys and interviews to understand safety culture as an approach to identify possible strategies to improve patient safety in this setting. the study took place in one maternity service in two public hospitals in NSW, Australia. Concurrently, both hospitals were undergoing an organisational restructure which was part of a major health reform agenda. The priorities of the reform included improving the quality of care and patient safety; and, creating a more efficient health system by reducing administration inefficiencies and duplication. a descriptive case study using three approaches: the safety culture was identified to warrant improvement across all six safety culture domains. There was reduced infrastructure and capacity to support incident management activities required to improve safety, which was influenced by instability from the organisational restructure. There was a perceived lack of leadership at all levels to drive safety and quality and improving the safety culture was neither a key priority nor was it valued by the organisation. the safety culture was complex as was undertaking this study. We were unable to achieve a desired 60% response rate highlighting the limitations of using safety culture surveys in isolation as a strategy to improve safety culture. Qualitative interviews provided greater insight into the factors influencing the safety culture. The findings of this study provide evidence of the benefits of including qualitative methods with quantitative surveys when examining safety culture

Angra-1 probabilistic safety study-phase B

International Nuclear Information System (INIS)

Fernandes Filho, T.L.; Gibelli, S.M.O.

1988-05-01

This study represents the Phase B of the Angra-1 Probabilistic Safety Study and is the the final report prepared for the IAEA under Research Contract No. 3423/R2/RB. The three main items covered in this report are the establishment of interim safety goals, analysis of Angra-1 operational experience and development of emergency procedures to address severe accidents. For establishment of interim safety goals a methodology for calculating consequences and risks associated to the Angra-1 operation was developed based on the available data and codes. The proposed safety goals refer to the individual risk of early fatality for people living in the vicinity of the plant, colective risk of cancer fatalities for people living near the plant, the propobability of core melt occurrence and the probability of dominant accident sequences. (author) [pt

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

A study on safety climate at nuclear power plants

International Nuclear Information System (INIS)

Fukui, Hirokazu; Yoshida, Michio; Yoshiyama, Naohiro

2001-01-01

In the current study, we define safety climate as an organizational environment that induces members of the organization to give consideration to safety or take safety actions. It is of utmost importance that people holding managerial positions in an organization have a good understanding of the characteristics of the safety climate of the organization and implement safety promotion activities effectively. In the current research, we studied the rating scales and the characteristics of a safety climate. A survey was conducted, targeting technical engineers who belong to the three power stations of Kansai Electric Power Co., Inc. The questionnaire mainly consisted of questions concerning safety measures taken by individuals and questions concerning safety measures taken by the organization, to which the individuals belong. As a result of a factor analysis of the responses, we extracted five factors, namely, 'confidence in knowledge and skill', attitude of supervisors,' 'safety education in workplace', 'clarity of tasks' and 'safety confirmation/report'. In studying the rating scales of the safety climate, we selected five items from each of the above five factors, and used the total scores of the ratings of the five items as scores of each factor. Then, we examined the correlation between scores of personal factors and scores of organizational environment factors. We treated the scores of safety confirmation/report' and 'confidence in knowledge and skill', which are personal factors, as criterion variables, and the scores of 'attitude of supervisors', 'safety education in workplace' and 'clarity of tasks', which are organizational environment factors, as predictor variables. As a result, we found that levels of 'safety confirmation/report' and 'confidence in knowledge and skill' can be deduced from the scores of 'attitude of supervisors', 'safety education in workplace' and 'clarity of tasks.' Hence, we have decided to use these three organizational environment

Criticality safety basics, a study guide

Energy Technology Data Exchange (ETDEWEB)

V. L. Putman

1999-09-01

This document is a self-study and classroom guide, for criticality safety of activities with fissile materials outside nuclear reactors. This guide provides a basic overview of criticality safety and criticality accident prevention methods divided into three parts: theory, application, and history. Except for topic emphasis, theory and history information is general, while application information is specific to the Idaho National Engineering and Environmental Laboratory (INEEL). Information presented here should be useful to personnel who must know criticality safety basics to perform their assignments safely or to design critically safe equipment or operations. However, the guide's primary target audience is fissile material handler candidates.

Criticality safety basics, a study guide

International Nuclear Information System (INIS)

Putman, V.L.

1999-01-01

This document is a self-study and classroom guide, for criticality safety of activities with fissile materials outside nuclear reactors. This guide provides a basic overview of criticality safety and criticality accident prevention methods divided into three parts: theory, application, and history. Except for topic emphasis, theory and history information is general, while application information is specific to the Idaho National Engineering and Environmental Laboratory (INEEL). Information presented here should be useful to personnel who must know criticality safety basics to perform their assignments safely or to design critically safe equipment or operations. However, the guide's primary target audience is fissile material handler candidates

Comparative analysis of operation and safety of subcritical nuclear systems and innovative critical reactors; Analyse comparative du fonctionnement et de la surete de systemes sous-critiques et de reacteurs critiques innovants

Energy Technology Data Exchange (ETDEWEB)

Bokov, P.M

2005-05-01

The main goal of this thesis work is to investigate the role of core subcriticality for safety enhancement of advanced nuclear systems, in particular, molten salt reactors, devoted to both energy production and waste incineration/transmutation. The inherent safety is considered as ultimate goal of this safety improvement. An attempt to apply a systematic approach for the analysis of the subcriticality contribution to inherent properties of hybrid system was performed. The results of this research prove that in many cases the subcriticality may improve radically the safety characteristics of nuclear reactors, and in some configurations it helps to reach the 'absolute' intrinsic safety. In any case, a proper choice of subcriticality level makes all analyzed transients considerably slower and monotonic. It was shown that the weakest point of the independent-source systems with respect to the intrinsic safety is thermohydraulic unprotected transients, while in the case of the coupled-source systems the excess reactivity/current insertion events remain a matter of concern. To overcome these inherent drawbacks a new principle of realization of a coupled sub-critical system (DENNY concept) is proposed. In addition, the ways to remedy some particular safety-related problems with the help of the core sub-criticality are demonstrated. A preliminary safety analysis of the fast-spectrum molten salt reactor (REBUS concept) is also carried out in this thesis work. Finally, the potential of the alternative (to spallation) neutron sources for application in hybrid systems is examined. (author)

Safety certification of airborne software: An empirical study

International Nuclear Information System (INIS)

Dodd, Ian; Habli, Ibrahim

2012-01-01

Many safety-critical aircraft functions are software-enabled. Airborne software must be audited and approved by the aerospace certification authorities prior to deployment. The auditing process is time-consuming, and its outcome is unpredictable, due to the criticality and complex nature of airborne software. To ensure that the engineering of airborne software is systematically regulated and is auditable, certification authorities mandate compliance with safety standards that detail industrial best practice. This paper reviews existing practices in software safety certification. It also explores how software safety audits are performed in the civil aerospace domain. The paper then proposes a statistical method for supporting software safety audits by collecting and analysing data about the software throughout its lifecycle. This method is then empirically evaluated through an industrial case study based on data collected from 9 aerospace projects covering 58 software releases. The results of this case study show that our proposed method can help the certification authorities and the software and safety engineers to gain confidence in the certification readiness of airborne software and predict the likely outcome of the audits. The results also highlight some confidentiality issues concerning the management and retention of sensitive data generated from safety-critical projects.

Quality management of pharmacology and safety pharmacology studies

DEFF Research Database (Denmark)

Spindler, Per; Seiler, Jürg P

2002-01-01

to safety pharmacology studies, and, when indicated, to secondary pharmacodynamic studies, does not influence the scientific standards of studies. However, applying formal GLP standards will ensure the quality, reliability and integrity of studies, which reflect sound study management. It is important...... to encourage a positive attitude among researchers and academics towards these lines, whenever possible. GLP principles applied to the management of non-clinical safety studies are appropriate quality standards when studies are used in the context of protecting public health, and these quality standards...... of pharmacology studies (ICH S7A): primary pharmacodynamic, secondary pharmacodynamic and safety pharmacology studies, and guidance on the quality standards (expectations for GLP conformity) for these study types have been provided. Primary pharmacodynamic studies are the only study types that are fully exempt...

A study on safety climate at nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Fukui, Hirokazu [Institute of Nuclear Safety System Inc., Mihama, Fukui (Japan); Yoshida, Michio; Yoshiyama, Naohiro [Japan Institute for Group Dynamics, Fukuoka (Japan)

2001-09-01

In the current study, we define safety climate as an organizational environment that induces members of the organization to give consideration to safety or take safety actions. It is of utmost importance that people holding managerial positions in an organization have a good understanding of the characteristics of the safety climate of the organization and implement safety promotion activities effectively. In the current research, we studied the rating scales and the characteristics of a safety climate. A survey was conducted, targeting technical engineers who belong to the three power stations of Kansai Electric Power Co., Inc. The questionnaire mainly consisted of questions concerning safety measures taken by individuals and questions concerning safety measures taken by the organization, to which the individuals belong. As a result of a factor analysis of the responses, we extracted five factors, namely, 'confidence in knowledge and skill', attitude of supervisors,' 'safety education in workplace', 'clarity of tasks' and 'safety confirmation/report'. In studying the rating scales of the safety climate, we selected five items from each of the above five factors, and used the total scores of the ratings of the five items as scores of each factor. Then, we examined the correlation between scores of personal factors and scores of organizational environment factors. We treated the scores of safety confirmation/report' and 'confidence in knowledge and skill', which are personal factors, as criterion variables, and the scores of 'attitude of supervisors', 'safety education in workplace' and 'clarity of tasks', which are organizational environment factors, as predictor variables. As a result, we found that levels of 'safety confirmation/report' and 'confidence in knowledge and skill' can be deduced from the scores of 'attitude of supervisors', 'safety

Nuclear safety in countries that are candidate for entry to the European Union; La surete nucleaire dans les pays candidats a l'entree dans l'Union Europeenne

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-07-01

In this report, experts from countries members of the European Union have wished to give their collective opinion about nuclear safety in countries that are standing for integrating the E.U.. The investigated countries are Bulgaria, Hungary, Lithuania, Slovakia, Rumania, Slovenia and Czech Republic. This report is based on information given in international cooperation programmes such as Phare programmes as well as in bilateral contacts. 2 aspects are considered: regulatory authorities and the level of safety in operating nuclear power plants. This report does not deal with radioactive waste management nor with radiation protection. (A.C.)

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

International Nuclear Information System (INIS)

Bertsche, K.; Hoermann, E.

1991-01-01

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

Environmental Regulation and Food Safety: Studies of Protection ...

International Development Research Centre (IDRC) Digital Library (Canada)

Environmental Regulation and Food Safety: Studies of Protection and Protectionism. Book cover Environmental Regulation and Food Safety: Studies of Protection and Protectionism. Directeur(s) : Veena Jha. Maison(s) d'édition : Edward Elgar, IDRC. 1 janvier 2006. ISBN : 184542512X. 250 pages. e-ISBN : 155250185X.

Nitrogen-system safety study: Portsmouth Gaseous Diffusion Plant

International Nuclear Information System (INIS)

1982-07-01

The Department of Energy has primary responsibility for the safety of operations at DOE-owned nuclear facilities. The guidelines for the analysis of credible accidents are outlined in DOE Order 5481.1. DOE has requested that existing plant facilities and operations be reviewed for potential safety problems not covered by standard industrial safety procedures. This review is being conducted by investigating individual facilities and documenting the results in Safety Study Reports which will be compiled to form the Existing Plant Final Safety Analysis Report which is scheduled for completion in September, 1984. This Safety Study documents the review of the Plant Nitrogen System facilities and operations and consists of Section 4.0, Facility and Process Description, and Section 5.0, Accident Analysis, of the Final Safety Analysis Report format. The existing nitrogen system consists of a Superior Air Products Company Type D Nitrogen Plant, nitrogen storage facilities, vaporization facilities and a distribution system. The system is designed to generate and distribute nitrogen gas used in the cascade for seal feed, buffer systems, and for servicing equipment when exceptionally low dew points are required. Gaseous nitrogen is also distributed to various process auxiliary buildings. The average usage is approximately 130,000 standard cubic feet per day

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

International Nuclear Information System (INIS)

Svensson, Ola; Salo, Ilkka; Allwin, Pernilla

2004-11-01

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

Advice about the safety of graphite storage silos of Saint Laurent des Eaux facility; Avis sur la surete des silos de stockage de graphite de Saint Laurent des Eaux

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-07-01

This document is the safety analysis made by the national association of the local commissions of information about nuclear activities (ANCLI), about the safety of graphite storage silos of Saint Laurent des Eaux nuclear facility. The analysis covers: the operation safety and the accident hypothesis, the monitoring of indoor and outdoor contamination in routine situation, the geotechnical characteristics of the site environment, the isotopic inventory and the estimation of radioactivity in routine and accidental situation, the estimation of doses received by the population in accidental situation and the internal emergency plan. After examination of these different points, the scientific committee of the ANCLI considers that a new global evaluation of risks, which integrates more recent exposure data, has to be carried out. (J.S.)

Studying the Safety Impact of Autonomous Vehicles Using Simulation-Based Surrogate Safety Measures

Directory of Open Access Journals (Sweden)

Mark Mario Morando

2018-01-01

Full Text Available Autonomous vehicle (AV technology has advanced rapidly in recent years with some automated features already available in vehicles on the market. AVs are expected to reduce traffic crashes as the majority of crashes are related to driver errors, fatigue, alcohol, or drugs. However, very little research has been conducted to estimate the safety impact of AVs. This paper aims to investigate the safety impacts of AVs using a simulation-based surrogate safety measure approach. To this end, safety impacts are explored through the number of conflicts extracted from the VISSIM traffic microsimulator using the Surrogate Safety Assessment Model (SSAM. Behaviours of human-driven vehicles (HVs and AVs (level 4 automation are modelled within the VISSIM’s car-following model. The safety investigation is conducted for two case studies, that is, a signalised intersection and a roundabout, under various AV penetration rates. Results suggest that AVs improve safety significantly with high penetration rates, even when they travel with shorter headways to improve road capacity and reduce delay. For the signalised intersection, AVs reduce the number of conflicts by 20% to 65% with the AV penetration rates of between 50% and 100% (statistically significant at p<0.05. For the roundabout, the number of conflicts is reduced by 29% to 64% with the 100% AV penetration rate (statistically significant at p<0.05.

Contribution of operating feedback to probabilistic safety studies

International Nuclear Information System (INIS)

Guio, J.M. de; Lannoy, A.

1992-03-01

This paper presents the method used for PWR unit operation feedback analysis and its contribution to probabilistic safety studies. The targets were as follows: - use of failure data banks to assess reliability parameters, - use of event data banks to identify and quantify main system initiating events, - determination of a standard operating profile. These studies, performed in the context of nuclear power plant safety programs, prove useful not only to safety engineers but also to equipment experts, designers, operators and maintenance specialists. They constitute basic data for studies in all these areas or the departure point for new investigations. (authors). 3 figs., 3 tabs., 3 refs

Criticality safety studies at VTT Energy

International Nuclear Information System (INIS)

Roine, T.; Anttila, M.

1995-01-01

At VTT Energy a compact reactor physics calculation system is applied in many kind of problems. Generation of group constants for static and dynamic core calculations, flux and dose rate calculations as well as criticality safety studies are performed basically with the same codes. In the presentation a short overview of the wide variety of criticality safety problems analyzed at VTT Energy is given. The calculation system with some illustrative examples is also described. (12 refs., 1 tab.)

The German nuclear power plant safety study

International Nuclear Information System (INIS)

1979-01-01

With this study a new approach has been chosen, taking nuclear power plants as an example to assess and to describe the risks arising from the use of modern technology, including those hazards emanating from the rather hypothetical possibility of occurrence of very serious accidents. Following the definition of basic concepts and methods to be applied in risk assessment studied, as well as a brief account of the design and operating mode of nuclear power plants with PWRs', accidents and failures to be considered in a safety study are described. Using the course-of-event and fault tree analysis, the probability of fission product release as a consequence of failures in safety systems or of core meltdown is evaluated. Subsequently, the theoretical model for assessment of reactor accident consequences is presented, discussing such aspects as the dispersion of radioactivity in the atmosphere, the radiation dose model, safety and countermeasures, the model for the evaluation of health hazards as well as methods and calculations for estimating the reliability of risk assessments together with the remaining uncertainties. In an appendix to this study, the analyses presented in the study are discussed in the light of the TMI-2 event. This safety study showing the possibilities of detecting, keeping in check and minimizing harmful effects, can be regarded as a contribution to a better understanding of our modern, highly industrialised society, and eventually to an improvement of the quality of life. (GL) 891 GL/GL 892 MB [de

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

Energy Technology Data Exchange (ETDEWEB)

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

2004-11-15

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

Preliminary study on improving safety culture in Malaysian nuclear industries

International Nuclear Information System (INIS)

Ibrahim, Sabariah Kader; Lee, Y. E.

2012-01-01

This paper presents preliminary study on safety culture and its implementation in Malaysian nuclear industries by realizing the importance of safety culture; identification of important safety culture attributes; safety culture assessment and the practices to incorporate the identified safety culture attributes in organization. The first section of this paper explains the terms and definitions related to safety culture. Second, for the realization of importance of safety culture in organization, the international operational experiences emphasizing the importance of safety culture are described. Third, important safety culture attributes which are frequently cited in literature are provided. Fourth, methods to assess safety culture in operating organization are described. Finally, the practices to enhance the safety culture in an organization are discussed

Preliminary study on improving safety culture in Malaysian nuclear industries

Energy Technology Data Exchange (ETDEWEB)

Ibrahim, Sabariah Kader [KAIST, Daejeon (Korea, Republic of); Lee, Y. E. [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2012-10-15

This paper presents preliminary study on safety culture and its implementation in Malaysian nuclear industries by realizing the importance of safety culture; identification of important safety culture attributes; safety culture assessment and the practices to incorporate the identified safety culture attributes in organization. The first section of this paper explains the terms and definitions related to safety culture. Second, for the realization of importance of safety culture in organization, the international operational experiences emphasizing the importance of safety culture are described. Third, important safety culture attributes which are frequently cited in literature are provided. Fourth, methods to assess safety culture in operating organization are described. Finally, the practices to enhance the safety culture in an organization are discussed.

Review of studies on criticality safety evaluation and criticality experiment methods

International Nuclear Information System (INIS)

Naito, Yoshitaka; Yamamoto, Toshihiro; Misawa, Tsuyoshi; Yamane, Yuichi

2013-01-01

Since the early 1960s, many studies on criticality safety evaluation have been conducted in Japan. Computer code systems were developed initially by employing finite difference methods, and more recently by using Monte Carlo methods. Criticality experiments have also been carried out in many laboratories in Japan as well as overseas. By effectively using these study results, the Japanese Criticality Safety Handbook was published in 1988, almost the intermediate point of the last 50 years. An increased interest has been shown in criticality safety studies, and a Working Party on Nuclear Criticality Safety (WPNCS) was set up by the Nuclear Science Committee of Organisation Economic Co-operation and Development in 1997. WPNCS has several task forces in charge of each of the International Criticality Safety Benchmark Evaluation Program (ICSBEP), Subcritical Measurement, Experimental Needs, Burn-up Credit Studies and Minimum Critical Values. Criticality safety studies in Japan have been carried out in cooperation with WPNCS. This paper describes criticality safety study activities in Japan along with the contents of the Japanese Criticality Safety Handbook and the tasks of WPNCS. (author)

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

International Nuclear Information System (INIS)

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

2004-03-01

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

A study of passive safety conditions for fast reactor core

International Nuclear Information System (INIS)

Shimizu, Akinao

1991-01-01

A study has been made for passive safety conditions of fast reactor cores. Objective of the study is to develop a concept of a core with passive safety as well as a simple safety philosophy. A simple safety philosophy, which is wore easy to explain to the public, is needed to enhance the public acceptance for nuclear reactors. The present paper describes a conceptual plan of the study including the definition of the problem a method of approach and identification of tasks to be solved

Study of industry safety management

International Nuclear Information System (INIS)

Park, Pil Su

1987-06-01

This book deals with general remarks, industrial accidents, statistics of industrial accidents, unsafe actions, making machinery and facilities safe, safe activities, having working environment safe, survey of industrial accidents and analysis of causes, system of safety management and operations, safety management planning, safety education, human engineering such as human-machines system, system safety, and costs of disaster losses. It lastly adds individual protective equipment and working clothes including protect equipment for eyes, face, hands, arms and feet.

Safety Culture Enhancement Project. Final Report. A Field Study on Approaches to Enhancement of Safety Culture

Energy Technology Data Exchange (ETDEWEB)

Lowe, Andrew; Hayward, Brent (Dedale Asia Pacific, Albert Park VIC 3206 (Australia))

2006-08-15

This report documents a study with the objective of enhancing safety culture in the Swedish nuclear power industry. A primary objective of this study was to ensure that the latest thinking on human factors principles was being recognised and applied by nuclear power operators as a means of ensuring optimal safety performance. The initial phase of the project was conducted as a pilot study, involving the senior management group at one Swedish nuclear power-producing site. The pilot study enabled the project methodology to be validated after which it was repeated at other Swedish nuclear power industry sites, providing a broad-ranging analysis of opportunities across the industry to enhance safety culture. The introduction to this report contains an overview of safety culture, explains the background to the project and sets out the project rationale and objectives. The methodology used for understanding and analysing the important safety culture issues at each nuclear power site is then described. This section begins with a summary of the processes used in the information gathering and data analysis stage. The six components of the Management Workshops conducted at each site are then described. These workshops used a series of presentations, interactive events and group exercises to: (a) provide feedback to site managers on the safety culture and safety leadership issues identified at their site, and (b) stimulate further safety thinking and provide 'take-away' information and leadership strategies that could be applied to promote safety culture improvements. Section 3, project Findings, contains the main observations and output from the project. These include: - a brief overview of aspects of the local industry operating context that impinge on safety culture; - a summary of strengths or positive attributes observed within the safety culture of the Swedish nuclear industry; - a set of identified opportunities for further improvement; - the aggregated

Probabilistic studies for a safety assurance program

International Nuclear Information System (INIS)

Iyer, S.S.; Davis, J.F.

1985-01-01

The adequate supply of energy is always a matter of concern for any country. Nuclear power has played, and will continue to play an important role in supplying this energy. However, safety in nuclear power production is a fundamental prerequisite in fulfilling this role. This paper outlines a program to ensure safe operation of a nuclear power plant utilizing the Probabilistic Safety Studies

Activities on safety culture study. Study status in public and private sectors

International Nuclear Information System (INIS)

Makino, Maomi; Takano, Kenichi

2004-01-01

Around after entering in the 21st century, organizational accidents had occurred in Japan at various industries including nuclear industry, which were caused directly by unsafe action, human error and illegal conduct of personnel but there were problems in safety culture of organization such as slow retreat of safety system stimulated by management, schedule control and procedure management becoming a dead letter, lack of safety education, and workplace climate of schedule priority. This article referred to organizational factors common to many severe accidents and introduced safety culture study in public and private sectors to overcome those factors. Safety Culture Evaluation Support Tool (SCEST) was developed for self-evaluation of safety culture of organization as well as Organizational Reliability model (OR model) for analysis of initiation and propagation process of risk event. Safety diagnosis system and feedback type risk assessment system for promoting safe organizational climate and culture were also developed. (T. Tanaka)

Controlling safety at all stage of parcel lifetime

International Nuclear Information System (INIS)

Sert, Gilles; Aguilar, Jacques; Clemente, Colette; Sauron, Claire; Labergri, Fabien; Jacob, Emmanuel; Sallit, George; Lourtie, Guy

2012-01-01

This chapter is made of several small articles entitled: - 'L'etude des risques lies aux situations extremes pouvant survenir lors du transport des substances radioactives' (The investigation of risks related to extreme situations which may occur during radioactive material transport); - 'Une necessaire diversification de l'expertise: le role du Groupe permanent d'experts pour les transports' (A required diversification of expertise: the role of the permanent group of experts for transports); - 'Vers un nouveau consensus sur les methodes et les parametres de reference a retenir lors des agrements des modeles de colis destines au transport' (Towards a new consensus on methods and reference parameters to be retained during agreements of models of parcels designed for transport); - 'Le controle de la fabrication des emballages par l'ASN' (Control of packaging manufacturing by the ASN); - 'Concevoir et realiser un emballage destine au transport de substances radioactives: l'exemple de la societe ROBATEL' (Designing and manufacturing a package for nuclear material transport: the example of the ROBATEL company); - 'Les transports internes dans les installations nucleaires de base secretes' (Internal transports within secrete base nuclear installations); - 'Les operations de transport interne sur les sites nucleaires' (Transport operations within nuclear sites); - 'Cooperation entre les Autorites competentes britanniques et francaises en matiere de regulation de la surete du transport des substances radioactives' (Cooperation between British and French Authorities in charge of radioactive material transport safety regulation); - 'Inspections et sanctions en Belgique' (Inspections and sanctions in Belgium). While evoking regulations and research studies, the first article comments the various risks (mechanical and thermal risks, and risks related to radiation leakage) associated with radioactive material transport. In an interview, the chairman of the permanent group of

Safety Culture Enhancement Project. Final Report. A Field Study on Approaches to Enhancement of Safety Culture

International Nuclear Information System (INIS)

Lowe, Andrew; Hayward, Brent

2006-08-01

This report documents a study with the objective of enhancing safety culture in the Swedish nuclear power industry. A primary objective of this study was to ensure that the latest thinking on human factors principles was being recognised and applied by nuclear power operators as a means of ensuring optimal safety performance. The initial phase of the project was conducted as a pilot study, involving the senior management group at one Swedish nuclear power-producing site. The pilot study enabled the project methodology to be validated after which it was repeated at other Swedish nuclear power industry sites, providing a broad-ranging analysis of opportunities across the industry to enhance safety culture. The introduction to this report contains an overview of safety culture, explains the background to the project and sets out the project rationale and objectives. The methodology used for understanding and analysing the important safety culture issues at each nuclear power site is then described. This section begins with a summary of the processes used in the information gathering and data analysis stage. The six components of the Management Workshops conducted at each site are then described. These workshops used a series of presentations, interactive events and group exercises to: (a) provide feedback to site managers on the safety culture and safety leadership issues identified at their site, and (b) stimulate further safety thinking and provide 'take-away' information and leadership strategies that could be applied to promote safety culture improvements. Section 3, project Findings, contains the main observations and output from the project. These include: - a brief overview of aspects of the local industry operating context that impinge on safety culture; - a summary of strengths or positive attributes observed within the safety culture of the Swedish nuclear industry; - a set of identified opportunities for further improvement; - the aggregated results of the

Nanotechnology Safety Self-Study

Energy Technology Data Exchange (ETDEWEB)

Grogin, Phillip W. [Los Alamos National Laboratory

2016-03-29

Nanoparticles are near-atomic scale structures between 1 and 100 nanometers (one billionth of a meter). Engineered nanoparticles are intentionally created and are used in research and development at Sandia National Laboratories (SNL) and Los Alamos National Laboratory (LANL). This course, Nanotechnology Safety Self-Study, presents an overview of the hazards, controls, and uncertainties associated with the use of unbound engineered nanoscale particles (UNP) in a laboratory environment.

78 FR 64504 - Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety...

Science.gov (United States)

2013-10-29

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety and Health (NIOSH or..., Number 177, Pages 56235-56236. Contact Person for More Information: Price Connor, Ph.D., NIOSH Health...

Canadian Consumer Food Safety Practices and Knowledge: Foodbook Study.

Science.gov (United States)

Murray, Regan; Glass-Kaastra, Shiona; Gardhouse, Christine; Marshall, Barbara; Ciampa, Nadia; Franklin, Kristyn; Hurst, Matt; Thomas, M Kate; Nesbitt, Andrea

2017-10-01

Understanding consumers' food safety practices and knowledge supports food safety education for the prevention of foodborne illness. The objective of this study was to describe Canadian consumer food safety practices and knowledge. This study identifies demographic groups for targeted food safety education messaging and establishes a baseline measurement to assess the effectiveness of food safety interventions over time. Questions regarding consumer food safety practices and knowledge were included in a population-based telephone survey, Foodbook, conducted from November 2014 to March 2015. The results were analyzed nationally by age group and by gender. The results showed that approximately 90% of Canadians reported taking the recommended cleaning and separating precautions when handling raw meat to prevent foodborne illness. Only 29% of respondents reported using a food thermometer when cooking any meat, and even fewer (12%) reported using a food thermometer for small cuts of meat such as chicken pieces. The majority (>80%) of Canadians were aware of the foodborne illness risks related to chicken and hamburger, but fewer (poultry.

Flammable Gas Safety Self-Study 52827

Energy Technology Data Exchange (ETDEWEB)

Glass, George [Los Alamos National Laboratory

2016-03-17

This course, Flammable Gas Safety Self-Study (COURSE 52827), presents an overview of the hazards and controls associated with commonly used, compressed flammable gases at Los Alamos National Laboratory (LANL).

Modeling the Relationship between Safety Climate and Safety Performance in a Developing Construction Industry: A Cross-Cultural Validation Study.

Science.gov (United States)

Zahoor, Hafiz; Chan, Albert P C; Utama, Wahyudi P; Gao, Ran; Zafar, Irfan

2017-03-28

This study attempts to validate a safety performance (SP) measurement model in the cross-cultural setting of a developing country. In addition, it highlights the variations in investigating the relationship between safety climate (SC) factors and SP indicators. The data were collected from forty under-construction multi-storey building projects in Pakistan. Based on the results of exploratory factor analysis, a SP measurement model was hypothesized. It was tested and validated by conducting confirmatory factor analysis on calibration and validation sub-samples respectively. The study confirmed the significant positive impact of SC on safety compliance and safety participation , and negative impact on number of self-reported accidents/injuries . However, number of near-misses could not be retained in the final SP model because it attained a lower standardized path coefficient value. Moreover, instead of safety participation , safety compliance established a stronger impact on SP. The study uncovered safety enforcement and promotion as a novel SC factor, whereas safety rules and work practices was identified as the most neglected factor. The study contributed to the body of knowledge by unveiling the deviations in existing dimensions of SC and SP. The refined model is expected to concisely measure the SP in the Pakistani construction industry, however, caution must be exercised while generalizing the study results to other developing countries.

Case study: the Argentina Road Safety Project: lessons learned for the decade of action for road safety, 2011-2020.

Science.gov (United States)

Raffo, Veronica; Bliss, Tony; Shotten, Marc; Sleet, David; Blanchard, Claire

2013-12-01

This case study of the Argentina Road Safety Project demonstrates how the application of World Bank road safety project guidelines focused on institution building can accelerate knowledge transfer, scale up investment and improve the focus on results. The case study highlights road safety as a development priority and outlines World Bank initiatives addressing the implementation of the World Report on Road Traffic Injury's recommendations and the subsequent launch of the Decade of Action for Road Safety, from 2011-2020. The case study emphasizes the vital role played by the lead agency in ensuring sustainable road safety improvements and promoting the shift to a 'Safe System' approach, which necessitated the strengthening of all elements of the road safety management system. It summarizes road safety performance and institutional initiatives in Argentina leading up to the preparation and implementation of the project. We describe the project's development objectives, financing arrangements, specific components and investment staging. Finally, we discuss its innovative features and lessons learned, and present a set of supplementary guidelines, both to assist multilateral development banks and their clients with future road safety initiatives, and to encourage better linkages between the health and transportation sectors supporting them.

Safety analysis and related studies

International Nuclear Information System (INIS)

Lelievre, J.

1979-12-01

Several examples of reactor safety studies are given. For light water reactors, the consequences of loss of coolant, the disposition of the fuel elements and the behaviour under irradiation of the steels used for containment are described. For fast reactors, the disposition of fuel elements in the case of cooling accidents and sodium fies are described. Examples given of studies not specific to a particular reactor type include studies of non-destructive testing and those of reliability

The advanced neutron source facility: Safety philosophy and studies

International Nuclear Information System (INIS)

Greene, S.R.; Harrington, R.M.

1988-01-01

The Advanced Neutron Source (ANS) is currently the only new civilian nuclear reactor facility proposed for construction in the United States. Even though the thermal power of this research-oriented reactor is a relatively low 300 MW, the design will undoubtedly receive intense scrutiny before construction is allowed to proceed. Safety studies are already under way to ensure that the maximum degree of safety in incorporated into the design and that the design is acceptable to the Department of Energy (DOE) and can meet the Nuclear Regulatory Commission regulations. This document discusses these safety studies

Patient safety: Safety culture and patient safety ethics

DEFF Research Database (Denmark)

Madsen, Marlene Dyrløv

2006-01-01

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

Preliminary Study on the Revision of Nuclear Safety Policy Statement

International Nuclear Information System (INIS)

Lee, Y. E.; Lee, S. H.; Chang, H. S.; Choi, K. S.; Jung, S. J.

2011-01-01

Nuclear safety policy in Korea is currently declared in the Nuclear Safety Charter as the highest tier document and safety principles and directions are announced in the Nuclear Safety Policy Statement. As the circumstances affecting on the nuclear safety policy change, it needs to revise the Statement. This study aims to develop the revised Nuclear Safety Policy Statement to declare that securing safety is a prerequisite to the utilization of nuclear energy, and that all workers in nuclear industry and regulatory body must adhere to the principle of priority to safety. As a result, two different types of revision are being prepared as of August. One is based on the spirit of Nuclear Safety Charter as well as the direction of future-oriented safety policies including the changes in the environment after declaration of the Statement. The other is to declare the fundamental safety objective and safety principles as the top philosophy of national nuclear safety policy by adopting the '10 Safety Principles in IAEA Safety Fundamental' instead of the current Charter. Both versions of revision are subject to further in-depth discussion. However once the revision is finalized and declared, it would be useful to accomplish effectively the organizational responsibilities and to enhance the public confidence in nuclear safety by performing the regulatory activities in a planned and systematic manner and promulgating the government's dedication to priority to safety

Progress in the development of methodology for fusion safety systems studies

International Nuclear Information System (INIS)

Ho, S.K.; Cambi, G.; Ciattaglia, S.; Fujii-e, Y.; Seki, Y.

1994-01-01

The development of fusion safety systems-study methodology, including the aspects of schematic classification of overall fusion safety system, qualitative assessment of fusion system for identification of critical accident scenarios, quantitative analysis of accident consequences and risk for safety design evaluation, and system-level analysis of accident consequences and risk for design optimization, by a consortium of international efforts is presented. The potential application of this methodology into reactor design studies will facilitate the systematic assessment of safety performance of reactor designs and enhance the impacts of safety considerations on the selection of design configurations

Project safety studies - nuclear waste management (PSE)

International Nuclear Information System (INIS)

1981-10-01

The project 'Safety Studies-Nuclear Waste Management' (PSE) is a research project performed by order of the Federal Minister for Research and Technology, the general purpose of which is to deepen and ensure the understanding of the safety aspects of the nuclear waste management and to prepare a risk analysis which will have to be established in the future. Owing to this the project is part of a series of projects which serve the further development of the concept of nuclear waste management and its safety, and which are set up in such a way as to accompany the realization of that concept. This report contains the results of the first stage of the project from 1978 to mid-1981. (orig./RW) [de

Coordination and carrying out of environment radioactivity measurement programmes in a radiological emergency situation, exploitation and restitution of results - Assessment of IRSN's actions and perspectives

International Nuclear Information System (INIS)

Dubiau, Ph.

2010-01-01

After having recalled the content of the interdepartmental 'measurement directive' which defines the legal framework of radioactivity measurements in case of a radiological emergency situation, this report described the actions performed by the IRSN (Institut de Radioprotection et de Surete Nucleaire, the French Radioprotection and Nuclear Safety Institute) and concerning these measurements. It discusses how the measurement strategy is defined depending on the accident characteristics and on the environment. It discusses how measurement results are interpreted, and evokes some constraints and limits for this strategy during the emergency phase. A laboratory vehicle is briefly presented which enables sample preparation and measurement by various analysis techniques

Nuclear safety in countries that are candidate for entry to the European Union; La surete nucleaire dans les pays candidats a l'entree dans l'Union Europeenne

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-07-01

In this report, experts from countries members of the European Union have wished to give their collective opinion about nuclear safety in countries that are standing for integrating the E.U.. The investigated countries are Bulgaria, Hungary, Lithuania, Slovakia, Rumania, Slovenia and Czech Republic. This report is based on information given in international cooperation programmes such as Phare programmes as well as in bilateral contacts. 2 aspects are considered: regulatory authorities and the level of safety in operating nuclear power plants. This report does not deal with radioactive waste management nor with radiation protection. (A.C.)

A study on optimization of the nuclear safety system

International Nuclear Information System (INIS)

Lee, Sang Hoon; Koh, Byung Joon; Kim, Jin Soo; Kim, Byoung Do; Cho, Seong Won; Kwon, Seog Kwon; Choi, Kwang Sik

1986-12-01

The number of nuclear facilities (nuclear power plants, research reactors, nuclear fuel facilities) under construction or in operation in Korea continues to increase and this has brought about increased importance and concerns toward nuclear safety in Korea. Also, domestic nuclear related organizations are increasingly carrying out the design/construction of nuclear power plants and the development /supply of nuclear fuels. In order to flexibly respond to these changes and to suggest direction to take, it is necessary to re-examine the current nuclear safety regulation system. This study is carried out in two stages and this report describes the results of the analysis and the assessment of the nuclear licencing system of such foreign countries as sweden and German, as the first of the two. In this regard, this study includes the analysis on the backgrounds on the choice of nuclear licensing system, the analysis on the licensing procedures, the analysis on the safety inspection system and the enforcement laws, the analysis on the structure and function of the regulatory, business and research organizations as well as the analysis on the relationship between the safety research and the regulatory duties. In this study, the German safety inspection system and the enforcement procedures and the Swedish nuclear licensing system are analyzed in detail. By comparing and assessing the finding with the current Korea Nuclear Licensing System, this study points out some reform measures of the Korean system that needs to improved. With the changing situations in mind, this study aims to develop the nuclear safety regulation system optimized for Korean situation by re-examining the current regulation system. (Author)

Thermal-hydraulic analysis of total loss of steam generator feed water in WWER-440

International Nuclear Information System (INIS)

Sabotinov, L.; Cadet-Mercier, S.

2001-01-01

The analysis is carried out for a WWER-440/V270 with upgraded primary safety valves (replacement of the existing PRZ safety valves with Pilot Operated Relief Valves (PORV) of the type SEBIM (France)) The current analysis is focused on the scenario 'Total Loss of SGs Feed Water' with application of the operator action of primary system 'Feed and Bleed' in order to check the effectiveness of the installed pressurizer SEBIM valves and to verify that the operator can cool down the reactor system and cope with this accident. The calculations have been performed at the Institute of Protection and Nuclear Safety (IPSN) in Fontenay-aux-Roses with the computer code CATHARE 2 Version 1.3L1. CATHARE is a French best estimate thermal-hydraulic program for accident analysis in the light water nuclear reactors, developed with the participation of the IPSN (Institut de Protection et Surete Nucleaire), CEA (Commissariat a l'Energie Atomique), Framatome and EdF (Electricite de France). (author)

Study on some safety-related aspects of tyre use

NARCIS (Netherlands)

Jansen, S.T.H.; Schmeitz, A.J.C.; Maas, S.; Rodarius, C.; Akkermans, L.

2014-01-01

The tyre is a key component that affects road safety. The European commission has posted a tender aimed to study what measures on a European level can be taken in relation to the use of tyres to improve road safety. The results of this study, supported by a cost benefit analyses and carried out by

A study of software safety analysis system for safety-critical software

International Nuclear Information System (INIS)

Chang, H. S.; Shin, H. K.; Chang, Y. W.; Jung, J. C.; Kim, J. H.; Han, H. H.; Son, H. S.

2004-01-01

The core factors and requirements for the safety-critical software traced and the methodology adopted in each stage of software life cycle are presented. In concept phase, Failure Modes and Effects Analysis (FMEA) for the system has been performed. The feasibility evaluation of selected safety parameter was performed and Preliminary Hazards Analysis list was prepared using HAZOP(Hazard and Operability) technique. And the check list for management control has been produced via walk-through technique. Based on the evaluation of the check list, activities to be performed in requirement phase have been determined. In the design phase, hazard analysis has been performed to check the safety capability of the system with regard to safety software algorithm using Fault Tree Analysis (FTA). In the test phase, the test items based on FMEA have been checked for fitness guided by an accident scenario. The pressurizer low pressure trip algorithm has been selected to apply FTA method to software safety analysis as a sample. By applying CASE tool, the requirements traceability of safety critical system has been enhanced during all of software life cycle phases

COLD-SAT feasibility study safety analysis

Science.gov (United States)

Mchenry, Steven T.; Yost, James M.

1991-01-01

The Cryogenic On-orbit Liquid Depot-Storage, Acquisition, and Transfer (COLD-SAT) satellite presents some unique safety issues. The feasibility study conducted at NASA-Lewis desired a systems safety program that would be involved from the initial design in order to eliminate and/or control the inherent hazards. Because of this, a hazards analysis method was needed that: (1) identified issues that needed to be addressed for a feasibility assessment; and (2) identified all potential hazards that would need to be controlled and/or eliminated during the detailed design phases. The developed analysis method is presented as well as the results generated for the COLD-SAT system.

The decisions taken in 2012 by the ASN: additional requirements

International Nuclear Information System (INIS)

Lacoste, Andre-Claude; Comets, Marie-Pierre; Dumont, Jean-Jacques; Bourguignon, Michel; Jamet, Philippe

2012-01-01

After the publication of conclusions of the Additions Safety Assessments (ECS, evaluations complementaires de surete), this document gathers 32 decisions taken by the ASN in June 2012 which specify additional requirements for EDF nuclear power plants, AREVA installations, and some CEA reactors. These measures will lead to a significant strengthening of safety margins beyond their sizing. These decisions impose huge works to operators. They comprise the implementation of an organisation and the construction of premises resistant to a big event which would affect several installations. Other measures concern a deeper training of agents intervening in case of earthquake or severe accident, robust means of power supply for warehousing pools, efficient means to reduce accidental leakage of different compounds, the storing of fissile materials in an installation sufficiently strong to resist earthquakes, and improvements regarding the flood risk management and sodium fire risk management

Behavior-based safety on construction sites: a case study.

Science.gov (United States)

Choudhry, Rafiq M

2014-09-01

This work presents the results of a case study and describes an important area within the field of construction safety management, namely behavior-based safety (BBS). This paper adopts and develops a management approach for safety improvements in construction site environments. A rigorous behavioral safety system and its intervention program was implemented and deployed on target construction sites. After taking a few weeks of safety behavior measurements, the project management team implemented the designed intervention and measurements were taken. Goal-setting sessions were arranged on-site with workers' participation to set realistic and attainable targets of performance. Safety performance measurements continued and the levels of performance and the targets were presented on feedback charts. Supervisors were asked to give workers recognition and praise when they acted safely or improved critical behaviors. Observers were requested to have discussions with workers, visit the site, distribute training materials to workers, and provide feedback to crews and display charts. They were required to talk to operatives in the presence of line managers. It was necessary to develop awareness and understanding of what was being measured. In the process, operatives learned how to act safely when conducting site tasks using the designed checklists. Current weekly scores were discussed in the weekly safety meetings and other operational site meetings with emphasis on how to achieve set targets. The reliability of the safety performance measures taken by the company's observers was monitored. A clear increase in safety performance level was achieved across all categories: personal protective equipment; housekeeping; access to heights; plant and equipment, and scaffolding. The research reveals that scores of safety performance at one project improved from 86% (at the end of 3rd week) to 92.9% during the 9th week. The results of intervention demonstrated large decreases in

Nuclear Safety and Radiation Protection in France in 2005; La surete nucleaire et la radioprotection en France en 2005. Dossier de presse

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-04-15

In 2005, the Asn pursued its significant investment in radiation protection and reaffirms its ambition to become as efficient in radiation protection as it is in nuclear safety as of 2009. 2005 was a year of great progress for the Asn as it consolidated its organisation and working methods, in accordance with the 2005-2007 strategic plan it set for itself. The Asn continued progress in the field of radiation protection has given rise to various new regulations to improve the legislative and regulatory framework in this area. The Asn plans to step up its efforts to ensure better monitoring of patient exposure to ionizing radiation and to provide better management of radon-related risks, particularly in housing. Fully aware that its newfound power in this area requires outside evaluation, the Asn has asked the International Atomic Energy Agency (IAEA) to organize an I.R.R.S. (Integrated Regulatory Review Service) assignment consisting of a peer-conducted audit. The IAEA has confirmed that this audit will take place in November 2006. (N.C.)

Age and workers' perceptions of workplace safety: a comparative study.

Science.gov (United States)

Gyekye, Seth Ayim; Salminen, Simo

2009-01-01

The study examined the relationship between age and (i) safety perception; (ii) job satisfaction; (iii) compliance with safety management policies; and (iv) accident frequency. Participants were Ghanaian industrial workers (N=320) categorized into 4 age groups: 19-29 years; 30-39 years; 40-50 years; and 51 years and above. Workplace safety perception was assessed with Hayes, Perander, Smecko, and Trask's (1998) 50-item Work Safety Scale (WSS): a scale that effectively captures the dimensions identified by safety experts to influence perceptions of workplace safety. ANOVA was used to test for differences in the mean scores of the 4 groups. Post Hoc analysis revealed differences of statistical significance between the 2 younger cohorts and the 2 older cohorts. The results indicated a positive association between age and safety perception. Older workers had the best perceptions on safety, indicated the highest level of job satisfaction, were the most compliant with safety procedures, and recorded the lowest accident involvement rate. From a practical perspective, understanding age-related perceptions of workplace safety would benefit management's decisions regarding workers' adaptability, general work effectiveness, accident frequency, implementation of safety management policies, and handling of age-related accident characteristics.

Main lessons for FBR safety study from the CABRI experiments

International Nuclear Information System (INIS)

Sato, Ikken

2006-01-01

CABRI project has been carried out FBR safety study with international cooperation of five nations since 1978. The project consists of four periods such as CABRI-1, CABRI-2, CABRI-FAST and CABRI-RAFT. The objects and the main information for hypothetical core decay accident and safety study of fuel are described. The behavior of core decay accident was studied in the first period (CABRI-1), the safety study of fuel was investigated after the second period (CABRI-2). Change of phenomena at the initial process of core decay accident, comparison between analysis and data of fuel diffusion behavior of neutron horoscope by CABRI-2 experiment, representative in-core experiment under slow TOP conditions, the damaged and undamaged pin under slow TOP conditions, the exterior of CABRI and TREAT and the upper part of CABRI and TREAT reactor are shown. CABRI experiments changed to LWR safety study and a part of TREAT is stated. (S.Y.)

The French-German initiative for Chernobyl: Overview of the French-German initiative

Energy Technology Data Exchange (ETDEWEB)

Biesold, H.; Friederichs, H.G.; Pretzsch, G. [Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH (GRS), Dept. International Programmes, Berlin (Germany); Deville-Cavelin, G.; Lhomme, V.; Rutschkowsky, N.; Tirmarche, M. [Institut de Radioprotection et de Surete Nucleaire (IRSN), Dept. International Relations, 92 - Clamart (France); Bazyka, D.; Chabanyuk, V.; Seleznev, A. [Chornobyl Center (CC), Kiev regoin (Ukraine); Kellerer, A.M. [Munchen Univ., Strahlenbiologisches Institut (Germany)

2006-07-01

- Purpose: The main purpose of the French-German Initiative is to assist in the collection and validation of the existing data in Ukraine, Belarus and Russia for developing a reliable and objective basis useful for the planning of counter-measures, for information of the public, and for future work. - Coordination: GRS (Gesellschaft fuer Anlagen- und Reaktorsicherheit), supported in programme 3 by SBI (Strahlenbiologisches Institut der Universitaet Muenchen) and IRSN (Institut de radioprotection et de surete nucleaire) are coordinating the projects on the Western side. The CC (Chernobyl Center for Nuclear Safety, Radioactive Waste and Radioecology) as Eastern coordinator is also the beneficiary. German Support by Bundesministerium fuer Umwelt, Naturschutz und Reaktorsicherheit (BMU), Vereinigung Deutscher Elektrizitaetswerke (VDEW) e.V.; French Support by Institut de radioprotection et de surete nucleaire (IRSN), Electricite de France (EdF). - Programmes: Three scientific and technical co-operation programmes are financed with a total budget of about 6 million Euro within the frame work of the French- German Initiative: Programme 1: SARCOPHAGUS: Safety of the Chernobyl 'Sarcophagus', Programme 2: RADIOECOLOGY: Study of the radioecological consequences of the accident,Programme 3: HEALTH: Study of health effects. - Background: At the IAEA conference in Vienna in April 1996 - 10 years after the Chernobyl accident - the French and German Environment Ministers jointly announced their co-operation initiative with the Ukraine, Belarus and Russia over scientific programmes concerning the aftermath of the Chernobyl disaster. Numerous scientific studies have been conducted in the affected republics of the former USSR with and without the participation of international organisations, but largely with insufficient real co-ordination. For some of the studies, results have never been publicly documented. There are still incoherent or even contradictory reports on the

Status of conceptual safety design study of Japanese sodium-cooled fast reactor

International Nuclear Information System (INIS)

Kubo, Shigenobu; Kurisaka, Kenichi; Niwa, Hajime; Shimakawa, Yoshio

2005-01-01

In this paper, the current conceptual safety design and related evaluation of Japanese Sodium-cooled Fast Reactor which is studied in the framework of the Feasibility Study (FS) on commercialized Fast Reactor Cycle Systems in Japan are described. The purpose of the safety design is to establish a feasible safety concept of FBR which aims at a sustainable energy source of the next generations. The safety targets and the safety design principle are set aiming at realizing worldwide acceptability of the safety level. The basic safety design concept, which can meet the safety targets, was formulated taking along with the defense-in-depth philosophy as the basic safety design principle. In order to cope with wide range of energy and resource demands, there are some various designs both of oxide and metal fuel for JSFR. Some analytical results of typical design basis events, design extension conditions and core damage frequency estimation show the feasibility of the safety design concept for them. (author)

Studies on Labour Safety in Construction Sites

Directory of Open Access Journals (Sweden)

S. Kanchana

2015-01-01

Full Text Available Construction industry has accomplished extensive growth worldwide particularly in past few decades. For a construction project to be successful, safety of the structures as well as that of the personnel is of utmost importance. The safety issues are to be considered right from the design stage till the completion and handing over of the structure. Construction industry employs skilled and unskilled labourers subject to construction site accidents and health risks. A proper coordination between contractors, clients, and workforce is needed for safe work conditions which are very much lacking in Indian construction companies. Though labour safety laws are available, the numerous accidents taking place at construction sites are continuing. Management commitment towards health and safety of the workers is also lagging. A detailed literature study was carried out to understand the causes of accidents, preventive measures, and development of safe work environment. This paper presents the results of a questionnaire survey, which was distributed among various categories of construction workers in Kerala region. The paper examines and discusses in detail the total working hours, work shifts, nativity of the workers, number of accidents, and type of injuries taking place in small and large construction sites.

Studies on Labour Safety in Construction Sites

Science.gov (United States)

Kanchana, S.; Sivaprakash, P.; Joseph, Sebastian

2015-01-01

Construction industry has accomplished extensive growth worldwide particularly in past few decades. For a construction project to be successful, safety of the structures as well as that of the personnel is of utmost importance. The safety issues are to be considered right from the design stage till the completion and handing over of the structure. Construction industry employs skilled and unskilled labourers subject to construction site accidents and health risks. A proper coordination between contractors, clients, and workforce is needed for safe work conditions which are very much lacking in Indian construction companies. Though labour safety laws are available, the numerous accidents taking place at construction sites are continuing. Management commitment towards health and safety of the workers is also lagging. A detailed literature study was carried out to understand the causes of accidents, preventive measures, and development of safe work environment. This paper presents the results of a questionnaire survey, which was distributed among various categories of construction workers in Kerala region. The paper examines and discusses in detail the total working hours, work shifts, nativity of the workers, number of accidents, and type of injuries taking place in small and large construction sites. PMID:26839916

Nuclear installations safety and protection: thirty years of researches on earthquakes at the IRSN; Surete et protection des installations nucleaires: trente ans de recherches a l'IRSN sur les seismes

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-03-01

Every years more than one hundred earthquakes occur in France. Taking into account this risk is essential for the safety of nuclear installations. In this context the IRSN develops research programs on earthquakes and realizes evolutions of safety procedures. This paper presents three sheets of researches realized by the IRSN on earthquakes risk assessment in the nuclear installations design and exploitation and the example of the Saint-Die earthquake. (A.L.B.)

Fusion-reactor blanket-material safety-compatibility studies

International Nuclear Information System (INIS)

Jeppson, D.W.; Muhlestein, L.D.; Keough, R.F.; Cohen, S.

1982-11-01

Blanket material selection for fusion reactors is strongly influenced by the desire to minimize safety and environmental concerns. Blanket material safety compatibility studies are being conducted to identify and characterize blanket-coolant-material interactions under postulated reactor accident conditions. Recently completed scoping compatibility tests indicate that : (1) ternary oxides (LiAlO 2 , Li 2 ZrO 3 , Li 2 SiO 3 , Li 4 SiO 4 and LiTiO 3 ) at postulated blanket operating temperatures are compatible with water coolant, while liquid lithium and Li 7 Pb 2 alloy reactions with water generate heat, aerosol and hydrogen; (2) lithium oxide and Li 17 Pb 83 alloy react mildly with water requiring special precautions to control hydrogen release; (3) liquid lithium reacts substantially, while Li 17 Pb 83 alloy reacts mildly with concrete to produce hydrogen; and (4) liquid lithium-air reactions present some major safety concerns

Review of light--water reactor safety studies. Volume 3 of health and safety impacts of nuclear, geothermal, and fossil-fuel electric generation in California

International Nuclear Information System (INIS)

Nero, A.V.; Farnaam, M.R.K.

1977-01-01

This report summarizes and compares important studies of light-water nuclear reactor safety, emphasizing the Nuclear Regulatory Commission's Reactor Safety Study, work on risk assessment funded by the Electric Power Research Institute, and the Report of the American Physical Society study group on light-water reactor safety. These reports treat risk assessment for nuclear power plants and provide an introduction to the basic issues in reactor safety and the needs of the reactor safety research program. Earlier studies are treated more briefly. The report includes comments on the Reactor Safety Study. The manner in which these studies may be used and alterations which would increase their utility are discussed

Preliminary Study on the Development of Quantitative Safety Culture Index

International Nuclear Information System (INIS)

Lee, Young Eal; Kim, Hun Sil; Ahn, Nam Sung

2005-01-01

Safety culture is that assembly of characteristics and attitudes in organizations and individuals which establishes that, as an overriding priority, nuclear plant safety issues receive the attention warranted by their significance. Because it needs to be recognized as the most significant consciousness to achieve the nuclear safety performance, Korean government and nuclear power generation company have tried to develop the practical method to improve the safety culture from the long term point view. In this study, based on the site interviews to define the potential issues on organizational behavior for the safe operation and the survey on the level of safety culture of occupied workers are conducted. Survey results are quantified as a few indicators of nuclear safety by the statistical method and it can be simulated by the dynamic modeling as time goes on. Currently index and dynamic modeling are still being developed, however, results can be used to suggest the long term strategy which safety is clearly integrated into all activities in the nuclear organization

Safety properties test data selection from an algebraic model of Lustre programs; Selection de tests de proprietes de surete a partir d'une modelisation algebrique de programmes lustre

Energy Technology Data Exchange (ETDEWEB)

Hsiao, N.Ch

1995-07-01

In the context to validate an industrial software, which is a set of reactive programs, we are confronted with the safety properties verification problem. This thesis reports an experience in which our goal is to generate the test data satisfying a safety property. The software to be validated is designed with the SAGA tool, in which a view can be regarded as a program of a programming language called LUSTRE. We adapt a test data generation tool called LOFT to this kind of programs. In this way, we consider the functional testing method on which the LOFT tool is based. Given any LUSTRE program, we try to give it an algebraic model because LOFT treats algebraic specifications. So, our task consists In defining a formal framework in which any LUSTRE program can be translated into a LOFT module: based on an operational semantics of the LUSTRE language, the flow types 'T-flow' are specified with the constructive algebraic formalism, then implemented in a LOFT modules base. Next, in a test selection process assisted by LOFT, a safety property Is expressed by an equation to join other control hypotheses, and to guide the test data selection. Some concrete test data set are generated in this way on some significant examples. This experience confirm the feasibility of formal method on test data selection for the reactive programs. (author)

Study Of Safety Management By Using Gis In Coimbatore

Directory of Open Access Journals (Sweden)

S. Kanchana

2015-08-01

Full Text Available The safety management is very important in the process of construction .The traditional methods of construction safety control cannot meet the construction of big project. To ensure the safety of construction and reduce accidents in the process of construction the current situation and problems we face in construction safety management should be studied first. And then the project risk warning mechanism based on the GIS is constructed according to the problems we faced to achieve visual monitoring and warning of construction safety risk management and to provide decision support for construction. This project aims to develop a web-based spatial decision support system model for proactive health and safety management in linear construction projects. 5 Currently health and safety management is usually performed reactively instead of proactive management since hazard identification and risk assessment is mostly performed on paper based documents that are not effectively used at site. An information system relates to a chain of operations lead to planning the observation and collection of data to storage and analysis of data to the use of derived information in decision-making processes. To create a web-based free and open sourced GIS that can work with different data formats by exchanging and presenting data as a real-time map on web.

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. Fourth National Report on Compliance with the Joint Convention Obligations. France

International Nuclear Information System (INIS)

2011-09-01

The Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management, hereinafter referred to as the 'Joint Convention', is the result of international discussions that followed the adoption of the Convention on Nuclear Safety, in 1994. France signed the Joint Convention at the General Conference of the International Atomic Energy Agency (IAEA) held on 29 September 1997, the very first day the Joint Convention was opened for signature. She approved it on 22 February 2000 and filed the corresponding instruments with the IAEA on 27 April 2000. The Joint Convention entered into force on 18 June 2001. For many years, France has been taking an active part in the pursuit of international actions to reinforce nuclear safety and considers the Joint Convention to be a key step in that direction. The fields covered by the Joint Convention have long been part of the French approach to nuclear safety. This report is the fourth of its kind. It is published in accordance with Article 32 of the Joint Convention and presents the measures taken by France to meet each of her obligations set out in the Convention. The facilities and radioactive materials covered by the Joint Convention are much diversified in nature and are controlled in France by different regulatory authorities (see Section E). Over and above a specific threshold of radioactive content, a facility is referred to as a 'basic nuclear facility' (installation nucleaire de base - INB) and placed under the control of the French Nuclear Safety Authority (Autorite de surete nucleaire - ASN). Below that threshold and provided that the facility involved falls under a category of the nomenclature of classified facilities for other purposes than their radioactive materials, any facility may be considered as a 'classified facility on environmental-protection grounds' (installation classee pour la protection de l'environnement - ICPE) and placed under the control of the Ministry for the

Safety of pressurized water reactors: problems and corresponding studies

International Nuclear Information System (INIS)

Cogne, F.

1976-01-01

The author recalls the safety problems subject to researches in the CEA, either because of their importance or because studies made abroad were not sufficiently developed or were classified or in order to acquire an independent judgement when safety is concerned. Those problems and studies are submitted referring to the 3 existing shields between man and dangerous materials: fuel element can, thermal shield, (pressure vessel and pipes), biological shield of which the behaviour is studied in connection with outside aggressions such as earthquakes, plane crashes, chemical explosions.. [fr

75 FR 5333 - Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety...

Science.gov (United States)

2010-02-02

...) Place: Embassy Suites Hotel, 1900 Diagonal Road, Alexandria, Virginia 22314, Telephone (703) 684-5900... matters related to the conduct of Study Section business and for the study section to consider safety and...

Abstract of results of safety study. Nuclear fuel cycle field in fiscal 2003

International Nuclear Information System (INIS)

2004-11-01

This report descried the results of studies of nuclear fuel cycle field (nuclear fuel facilities, seismic design, all subjects of environmental radiation and waste disposal, and subjects on nuclear fuel cycle in probabilistic safety assessment) in fiscal 2003 on the basis of the principle project of safety study (from fiscal 2001 to 2005). It consists of four chapters; the first chapter is outline of the principle of project, the second is objects and subjects of safety study in the nuclear fuel cycle field, the third list of questionnaire of results of safety study and the forth investigation of results of safety study in fiscal 2003. There are 49 lists, which include 22 reports on the nuclear fuel facility, one on the seismic design, 4 on the probabilistic safety assessment, 7 on the environmental radiation and 15 on the waste disposal. (S.Y.)

A feasibility study for Arizona's roadway safety management process using the Highway Safety Manual and SafetyAnalyst : final report.

Science.gov (United States)

2016-07-01

To enable implementation of the American Association of State Highway Transportation (AASHTO) Highway Safety Manual using : SaftetyAnalyst (an AASHTOWare software product), the Arizona Department of Transportation (ADOT) studied the data assessment :...

Dynamic modeling of the cesium, strontium, and ruthenium transfer to grass and vegetables

International Nuclear Information System (INIS)

Renaud, P.; Real, J.; Maubert, H.; Roussel-Debet, S.

1999-01-01

From 1988 to 1993, the Nuclear Safety and Protection Institute (Institut de Protection et de Surete Nucleaire -- IPSN) conducted experimental programs focused on transfers to vegetation following accidental localized deposits of radioactive aerosols. In relation to vegetable crops (fruit, leaves, and root vegetables) and meadow grass these experiments have enabled a determination of the factors involved in the transfer of cesium, strontium, and ruthenium at successive harvests, or cuttings, in respect of various time lags after contamination. The dynamic modeling given by these results allows an evaluation of changes in the mass activity of vegetables and grass during the months following deposit. It constitutes part of the ASTRAL post-accident radioecology model

Safety study of PCC 2140 and ALILOG 21 used as part of safety measurement systems

International Nuclear Information System (INIS)

Meriaux, Pierre; Adnot, Serge; Rayrolles, Catherine.

1978-03-01

The PCC 2140 and ALILOG 21 equipment may be used at C.E.A. or E.D.F., as part of safety measurement systems. In a study of a similar, but earlier equipment, it was noticed that certain types of failures caused the system to switch to the least sensitive measurement range, which was detrimental to safety. This report analyses failure modes leading to unsafe failures and evaluates the risks ran into taking in account tests during use [fr

Empirical Analysis of Construction Safety Climate - A Study

OpenAIRE

S.V.S.RAJA PRASAD; K.P.REGHUNATH

2010-01-01

Safety in the construction industry has always been a major issue. Though much improvement in construction safety has been achieved, the industry still continues to lag behind most other industries with regard to safety. The safety climate of any organization consists of employee’s attitudes towards and perceptions of, health and safety behavior. Construction workers attitudes towards safety are influenced by their perceptions of risk, management, safety rulesand procedures. A measure of safe...

The impact of automation on operator performance. An explorative study

International Nuclear Information System (INIS)

Tasset, Daniel; Charron, Sylvie; Miberg, Ann-Britt; Hollnagel, Erik

1999-01-01

This study addresses the issue of human-automation interaction in nuclear power plant control rooms. It was initiated by the Institut de Protection et de Surete Nucleaire (IPSN - France) in 1996, and has been carried out in a co-operation between the Institutt for Energiteknikk (IFE) and IPSN, 1996-1998. The purpose of the study is to contribute to the understanding of how automatic systems affect operator performance in nuclear power plants. The results of the project will be used in two ways. First, they will support the identification of particular human-automation issues of interest for future human-automation studies. Second, they will be used by IPSN to initiate the development of a knowledge-based aimed at supporting the conduction of comparative analyses between different human-automation set-ups in French nuclear power plants (author) (ml)

Contractors’ Attitude towards Enhancing Safety Performance: Case Study on Construction Firms in Penang

Directory of Open Access Journals (Sweden)

Ulang N. Md

2014-01-01

Full Text Available A qualitative study was conducted to investigate the contractors’ attitude towards enhancing the safety performance in construction site. Despite the fact that there are many safety initiatives established by the government, the rates of accidents are still in a critically high condition. Thus the purpose of this research is to study the contractors’ attitude towards enhancing the implementation of safety management system in construction site in order to increase the safety awareness of construction practitioners in construction site and improve the safety condition of construction sites. This study is conducted through oral interviews with the construction practitioners, and visual inspection of construction sites. The attitudes of contractors are evaluated from 3 aspects: Contractors’ efforts in implement and enforce the safety rules, Contractors efforts in overcoming the rate of accidents, and Reasons given by the contractors for not implement safety law.

Studying the Safety Impact of Autonomous Vehicles Using Simulation-Based Surrogate Safety Measures

OpenAIRE

Morando, Mark Mario; Tian, Qingyun; Truong, Long T.; Vu, Hai L.

2018-01-01

Autonomous vehicle (AV) technology has advanced rapidly in recent years with some automated features already available in vehicles on the market. AVs are expected to reduce traffic crashes as the majority of crashes are related to driver errors, fatigue, alcohol, or drugs. However, very little research has been conducted to estimate the safety impact of AVs. This paper aims to investigate the safety impacts of AVs using a simulation-based surrogate safety measure approach. To this end, safety...

77 FR 75633 - Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety...

Science.gov (United States)

2012-12-21

... (Closed). 8:00 a.m.-5:00 p.m., February 22, 2013 (Closed). Place: Embassy Suites, 1900 Diagonal Road... conduct of Study Section business and for the study section to consider safety and occupational health...

Why is patient safety so hard? A selective review of ethnographic studies.

Science.gov (United States)

Dixon-Woods, Mary

2010-01-01

Ethnographic studies are valuable in studying patient safety. This is a narrative review of four reports of ethnographic studies of patient safety in UK hospitals conducted as part of the Patient Safety Research Programme. Three of these studies were undertaken in operating theatres and one in an A&E Department. The studies found that hospitals were rarely geared towards ensuring perfect performances. The coordination and mobilization of the large number of inter-dependent processes and resources needed to support the achievement of tasks was rarely optimal. This produced significant strain that staff learned to tolerate by developing various compensatory strategies. Teamwork and inter-professional communication did not always function sufficiently well to ensure that basic procedural information was shared or that the required sequence of events was planned. Staff did not always do the right things, for a wide range of different reasons, including contestations about what counted as the right thing. Structures of authority and accountability were not always clear or well-functioning. Patient safety incidents were usually not reported, though there were many different reasons for this. It can be concluded that securing patient safety is hard. There are multiple interacting influences on safety, and solutions need to be based on a sound understanding of the nature of the problems and which approaches are likely to be best suited to resolving them. Some solutions that appear attractive and straightforward are likely to founder. Addressing safety problems requires acknowledgement that patient safety is not simply a technical issue, but a site of organizational and professional politics.

Advances made in French safety studies on pressurized water reactors

International Nuclear Information System (INIS)

Pelce, J.

1979-01-01

The programme of French safety studies on reactors is supposed to be known in its main outlines. A few recent results, obtained in different fields are presented. They concern the safety margins evaluation, the contamination transfer and the effect of external aggressions

Safety design study of fast breeder reactors in Japan

International Nuclear Information System (INIS)

Miura, M.; Inagaki, T.

1992-01-01

This paper reports on two fast breeder reactor (FBR) concepts, the tank type and the loop type, that have been studied as possible reactor designs to be used for a demonstration FBR (DFBR). The basic principle fo the DFBR design is to ensure plant safety through a defense-in-depth methodology. Improvements in the seismic and thermal stress designs have been attempted for both reactor concepts. The system design study strives to maximize the reliability of the safety-related systems and to rationalize commercialization of the plant

Report of Activity, 1997

International Nuclear Information System (INIS)

Lacoste, Andre-Claude; Livolant, Michel

1998-01-01

The Institute of Nuclear Protection and Safety (Institut de Protection et de Surete Nucleaire) - IPSN carries out research and expert studies needed in managing nuclear risk and consequences of nuclear events on population and environment, i.e. supervises the safety of installations, the prevention and study of accidents, the human health and environmental conditions, the safety of transport and has also the task of organizing the management of the crisis situations. IPSN has the mission of informing the public and participates in numerous international actions. Thus, since 1989 IPSN and its German counterpart, GRS, co-operate towards improving of the nuclear safety in Europe and developing a common approach of international issues. As acting for public authorities (government departments in charge with industry, environment, health or labor), IPSN grants technical authorizations on request of DSIN exploiters. The IPSN personnel amounts up to 1300 employees of whom around two thirds are engineers, researchers, physicians, agronomists, and veterinarians. This IPSN annual report contains in the 'Free Tribune' section two general papers entitled: 'The federalist role of research at IPSN' by Catherine Lecompte and 'The dose, a central issue in radioprotection debates' by Annie Sugier. Then five sub-reports follow: 1.The safety of nuclear facilities and radioactive wastes; 2.Crisis management; 3. The management of sensitive materials (protection and control of sensitive materials and safety analysis of the radioactive materials transport); 4.Protection of human health; 5.Environment protection. The report also presents the international activities, the cooperation IPSN/GRS, the budget, the staff and the human resource policy and the communication activity

Study on safety subsidiary objective of nuclear power plant in USA

International Nuclear Information System (INIS)

Chen Yan; Zhang Chunming; Fu Zhiwei; Song Wei; Li Chaojun; Wang Zhe; Zuo Jiaxu

2013-01-01

This paper reviewed the development of the quantitative safety objective and subsidiary objective in USA. The expressions of CDF and LERF were obtained according to NUREG-1150. The relationship between the subsidiary objective and the quantitative safety objective was derived. The method was compared with that used in NUREG-1860. The requirements of safety objective for the future nuclear power plant and the development of probabilistic safety analysis (PSA) technology in USA were studied and can be used as reference in China. (authors)

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

Science.gov (United States)

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

2008-10-01

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

The reactor safety study of experimental multi-purpose VHTR design

International Nuclear Information System (INIS)

Yasuno, T.; Mitake, S.; Ezaki, M.; Suzuki, K.

1981-01-01

Over the past years, the design works of the Experimental Very High Temperature Reactor (VHTR) plant have been conducted at Japan Atomic Energy Research Institute. The conceptual design has been completed and the more detailed design works and the safety analysis of the experimental VHTR plant are continued. The purposes of design studies are to show the feasibility of the experimental VHTR program, to specify the characteristics and functions of the plant components, to point out the R and D items necessary for the experimental VHTR plant construction, and to analyze the feature of the plant safety. In this paper the summary of system design and safety features of the experimental reactor are indicated. Main issues are the safety philosophy for the design basis accident, the accidents assumed and the engineered safety systems adopted in the design works

A study of RFID application impacts on medical safety.

Science.gov (United States)

Chang, She-I; Ou, Chin-Shyh; Ku, Cheng-Yuan; Yang, Morris

2008-01-01

With the international reform in medical management systems gaining ground worldwide, hospital management has gradually begun to shift its focus from providing expensive medical treatment to improving medical service quality and patient safety. In this study, we discuss the application of Radio Frequency Identification (RFID) and data integrating technology with the medical service, and examine whether or not this technology can enhance medical safety. We also discuss the possible benefits following the application of the RFID system. The findings show that the application of RFID to hospitals can actually generate benefits, which can be further divided into operational structure benefits, users' structure benefits, and organisational and environmental benefits. However, not all these benefits can achieve medical safety. Among them, only the operator and environmental benefits can play such roles. Nevertheless, the application of RFID can bring hospitals towards the integration of technology benefits and improved medical safety.

Bus safety study : a report to Congress.

Science.gov (United States)

2013-11-01

Section 20021(b) of the Moving Ahead for Progress for the 21st Century (MAP-21) legislation requires the Secretary of Transportation : to submit a report of the results of a Bus Safety Study to the Committee on Banking, Housing, and Urban Affai...

Safety in the ARIES Tokamak Design Study

International Nuclear Information System (INIS)

Herring, J.S.; Wong, C.P.-C.; Cheng, E.T.; Grotz, S.

1989-01-01

Safety is one of the primary goals of the ARIES Tokamak Design Study. Public safety goals are the achievement passive safety which is demonstrable in tests that could precede operation and the assurance that releases from accidents be passively limited such that no evacuation plan in necessary. Strategies for safety of the plant investment are factory fabrication, short construction times and a design such that no off-normal operational transient results in damage which could not be repaired in routine maintenance. ARIES-I, the first of three 'visions' of potential tokamak reactors, will use He at 5 MPa as a blanket coolant and SiC/composite ceramic for the first wall and blanket materials. Both the coolant and the structural material were chosen for their low activation, both in the short term after accidents and for long term waste management. The breeder, Li 4 SiO 4 , was also chosen for low activation. Contemporary plasma physics and aggressive technology are used in ARIES-I, which results in very high toroidal fields (24 T maximum at the coil). The stored TF energy will be about 130 GJ. A central concern is the safe discharge of this stored energy under electrical fault conditions and prevention of a failure in the magnet set from propagating into systems containing radioactive inventories. The TF coil system consists of 16 coils, each containing two separate windings powered by two independent power supplies. Arcs and shorts between the two power supply systems and across individual windings have been modeled. In addition, delay or failure in circuit breaker opening has been modeled. The safety impacts of LOCA, LOFA and disruptive events have also been evaluated. 8 refs., 4 figs., 7 tabs

77 FR 43090 - Safety and Occupational Health Study Section: Notice of Charter Renewal

Science.gov (United States)

2012-07-23

... Committee Act (Pub. L. 92-463) of October 6, 1972, that the Safety and Occupational Health Study Section... Secretary, Safety and Occupational Health Study Section, Department of Health and Human Services, 1600... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Safety and...

75 FR 42455 - Safety and Occupational Health Study Section: Notice of Charter Renewal

Science.gov (United States)

2010-07-21

... Committee Act (Pub. L. 92-463) of October 6, 1972, that the Safety and Occupational Health Study Section... Secretary, Safety and Occupational Health Study Section, Department of Health and Human Services, 1600... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Safety and...

EPR safety. Consideration of the internal and external hazards in the safety studies

International Nuclear Information System (INIS)

Gueguin, H.

2008-04-01

The author presents the main points of the Preliminary Safety Report of EDF on the EPR reactor safety. It concerns the considerations of the internal (fire, flood, explosions, pipes failures) and external (earthquakes, airplane falls, explosions, exceptional natural disasters, extreme meteorological conditions) damages. It presents how the safety report takes into account the aggression. (A.L.B.)

Fire safety study of Dodewaard and Borssele nuclear power plants

International Nuclear Information System (INIS)

1988-03-01

From the nuclear and conventional fire safety audits of both Dutch nuclear power plants performed under supervision of the Nuclear Safety Inspectorate and the Inspectorate for the Fire Services it turns out that the fire safety is sufficient however amenable for improvement. Besides a detailed description of the method of examination, the study 'Fire Safety' contains the results of the audit and 14 respectively 15 recommendations for improvement of the fire safety in Dodewaard and Borssele. The suggested recommendations which are applicable to both power plants are the following: fire fighting training for operators and guards, a complete emergency ventilation system of the control room, increase in the number of detectors and alarms, an increase in the quantity of water available for high-pressure fire fighting, improvement of fire barriers between several redundancies of nuclear safety systems, an investigation and possible improvement of the heat and radiation protection offered by presently used fire fighting suits. For Dodewaard a closed emergency staircase in the reactor building (secondary containment) is deemed necessary for personnel emergency escape routes and continued fire fighting if required

78 FR 24751 - Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety...

Science.gov (United States)

2013-04-26

... 14, 2013 (Closed) Place: Embassy Suites, 1900 Diagonal Road, Alexandria, Virginia 22314, Telephone... business and for the study section to consider safety and occupational health-related grant applications...

MELCOR 1.8.2 Analyses in Support of ITER's RPrS

International Nuclear Information System (INIS)

Brad J Merrill

2008-01-01

The International Thermonuclear Experimental Reactor (ITER) Program is performing accident analyses for ITER's 'Rapport Preliminaire de Surete' (Report Preliminary on Safety - RPrS) with a modified version of the MELCOR 1.8.2 code. The RPrS is an ITER safety document required in the ITER licensing process to obtain a 'Decret Autorisation de Construction' (a Decree Authorizing Construction - DAC) for the ITER device. This report documents the accident analyses performed by the US with the MELCOR 1.8.2 code in support of the ITER RPrS effort. This work was funded through an ITER Task Agreement for MELCOR Quality Assurance and Safety Analyses. Under this agreement, the US was tasked with performing analyses for three accident scenarios in the ITER facility. Contained within the text of this report are discussions that identify the cause of these accidents, descriptions of how these accidents are likely to proceed, the method used to analyze the consequences of these accidents, and discussions of the transient thermal hydraulic and radiological release results for these accidents

Simulation study of coal mine safety investment based on system dynamics

Institute of Scientific and Technical Information of China (English)

Tong Lei; Dou Yuanyuan

2014-01-01

To generate dynamic planning for coal mine safety investment, this study applies system dynamics to decision-making, classifying safety investments by accident type. It validates the relationship between safety investments and accident cost, by structurally analyzing the causality between safety investments and their influence factors. Our simulation model, based on Vensim software, conducts simulation anal-ysis on a series of actual data from a coalmine in Shanxi Province. Our results indicate a lag phase in safety investments, and that increasing pre-phase safety investment reduces accident costs. We found that a 24%increase in initial safety investment could help reach the target accident costs level 14 months earlier. Our simulation test included nine kinds of variation trends of accident costs brought by different investment ratios on accident prevention. We found an optimized ratio of accident prevention invest-ments allowing a mine to reach accident cost goals 4 months earlier, without changing its total investment.

Pilot Study on Harmonisation of Reactor Safety in WENRA Countries

International Nuclear Information System (INIS)

2003-03-01

Most of the objectives, set for the Pilot Study, were met. It can be concluded that the methodology was adequate for its purpose. National requirements on selected safety issues have been systematically compared and the major gaps and differences have been identified. Convenient overviews have been provided of differences and similarities between the countries. Furthermore, the conclusions are based on a safety justification and are detailed enough to provide input to a further more detailed analysis on the national level. It was not possible, however, to provide fully verified conclusions about the implementation of the reference levels in the different countries. This has to do with the following constraints on the study: In line with the Terms of Reference, the comparison of formal requirements did not address the more detailed use of criteria and methods to verify compliance. The same requirement could be enforced differently in different regulatory systems, and hence lead to different implementation. The Pilot Study also assessed the implementation, but it was not possible to do this in sufficient detail to identify such differences. The implementation was assessed on the basis of current knowledge of the respective regulatory body, but it was not possible to provide the panels with evidence of the implementation. For these reasons, conclusions about implemented safety provisions in the different countries should be drawn with precaution. The introduction of the panel assessments greatly improved the quality and consistency of the comparison assessments. Uncertainties in the assessments are mainly connected with lack of time to make a detailed analysis in some cases. The reliability of the assessments seems to be sufficient for the objectives of the Pilot Study. The introduction of the IAEA safety standards in the study proved to be helpful and provided confidence in the scope and strictness of the reference levels. This Pilot Study has contributed to

Study on operational safety issues in the Japanese disposal concept

International Nuclear Information System (INIS)

Suzuki, Satoru; Kitagawa, Yoshito; Hyodo, Hideaki; Kubota, Shigeru; Iijima, Masayoshi; Tamura, Akio; Ishiguro, Katsuhiko; Fujihara, Hiroshi

2014-01-01

In Japan, vitrified high-level radioactive waste (HLW) and certain types of low-level radioactive waste that results from the reprocessing of spent fuel and classified as TRU waste will be disposed of in deep geological formations. NUMO aims to ensure the safety of local residents and workers during the operational phase and after repository closure and will therefore establish a safety case for the geological disposal programme at the end of each stage of the stepwise siting process. Although the Japanese programme is still in the stage before initiation of the siting process, updating the generic (non-site-specific) safety case is required for building confidence among stakeholders. This study focuses on operational safety issues for the Japanese HLW disposal concept. (authors)

Preliminary study on functional performance of compound type multistage safety injection tank

International Nuclear Information System (INIS)

Bae, Youngmin; Kim, Young In; Kim, Keung Koo

2015-01-01

Highlights: • Functional performance of compound type multistage safety injection tanks is studied. • Effects of key design parameters are scrutinized. • Distinctive flow features in compound type safety injection tanks are explored. - Abstract: A parametric study is carried out to evaluate the functional performance of a compound type multistage safety injection tank that would be considered one of the components for the passive safety injection systems in nuclear power plants. The effects of key design parameters such as the initial volume fraction and charging pressure of gas, tank elevation, vertical location of a sparger, resistance coefficient, and operating condition on the injection flow rate are scrutinized along with a discussion of the relevant flow features. The obtained results indicate that the compound type multistage safety injection tank can effectively control the injection flow rate in a passive manner, by switching the driving force for the safety injection from gas pressure to gravity during the refill and reflood phases, respectively

Tritium safety study using Caisson Assembly (CATS) at TPL/JAEA

International Nuclear Information System (INIS)

Hayashi, T.; Kobayashi, K.; Iwai, Y.; Isobe, K.; Nakamura, H.; Kawamura, Y.; Shu, W.; Suzuki, T.; Yamada, M.; Yamanishi, T.

2008-01-01

Tritium confinement is required as the most important safety Junction for a fusion reactor. In order to demonstrate the confinement performance experimentally, an unique equipment, called CATS: Caisson Assembly for Tritium Safety study, was installed in Tritium Process Laboratory of Japan Atomic Energy Agency and operated for about 10 years. Tritium confinement and migration data in CATS have been accumulated and dynamic simulation code was accumulated using these data. Contamination and decontamination behavior on various materials and new safety equipment functions have been investigated under collaborations with a lot of laboratories and universities. (authors)

Safety benefits from CANDU reactor replacement - a case study

International Nuclear Information System (INIS)

Mottram, R.; Millard, J.W.F.; Purdy, P.

2011-01-01

Both total core replacement and core retubing have been used in the CANDU industry. For future plant refurbishments, based on experience both in new construction and in recent refurbishments, the concept of total core replacement has been revisited. This builds on practices for replacement of other large plant equipment like boilers. The Bruce CANDU reactors, with their local shield tanks built around the Calandria and containment closely located around that Calandria Shield Tank Assembly (CSTA), are believed to be good candidates for core replacement. A structured process was used to design a replacement CSTA suitable for Bruce A use. The work started with a study of opportunities for safety enhancements in the core. This progressed into design studies and related design assist safety analysis on the reactor. A key element of the work involved consideration of how verified features from later CANDU designs, and from our new reactor design work, could be tailored to fit this replacement core. The replacement reactor core brings in structural improvements in both calandria and end shield, and safety improvements like the natural circulation enhancing moderator cooling layout and further optimized reactivity layouts to improve shutdown system performance. Bruce Power are currently studying the business implications of this and retube techniques as part of preparation for future refurbishments. The work explained in this paper is in the context of the safety related changes and the work to choose and quantify them. (author)

Safety benefits from CANDU reactor replacement. A case study

International Nuclear Information System (INIS)

Mottram, R.; Millard, J.W.F.; Purdy, P.

2011-01-01

Both total core replacement and core retubing have been used in the CANDU industry. For future plant refurbishments, based on experience both in new construction and in recent refurbishments, the concept of total core replacement has been revisited. This builds on practices for replacement of other large plant equipment like boilers. The Bruce CANDU reactors, with their local shield tanks built around the Calandria and containment closely located around that Calandria Shield Tank Assembly (CSTA), are believed to be good candidates for core replacement. A structured process was used to design a replacement CSTA suitable for Bruce A use. The work started with a study of opportunities for safety enhancements in the core. This progressed into design studies and related design assist safety analysis on the reactor. A key element of the work involved consideration of how verified features from later CANDU designs, and from our new reactor design work, could be tailored to fit this replacement core. The replacement reactor core brings in structural improvements in both calandria and end shield, and safety improvements like the natural circulation enhancing moderator cooling layout and further optimized reactivity layouts to improve shutdown system performance. Bruce Power are currently studying the business implications of this and retube techniques as part of preparation for future refurbishments. The work explained in this paper is in the context of the safety related changes and the work to choose and quantify them. (author)

Ferrocyanide safety project ferrocyanide aging studies. Final report

International Nuclear Information System (INIS)

Lilga, M.A.; Hallen, R.T.; Alderson, E.V.

1996-06-01

This final report gives the results of the work conducted by Pacific Northwest National Laboratory (PNNL) from FY 1992 to FY 1996 on the Ferrocyanide Aging Studies, part of the Ferrocyanide Safety Project. The Ferrocyanide Safety Project was initiated as a result of concern raised about the safe storage of ferrocyanide waste intermixed with oxidants, such as nitrate and nitrite salts, in Hanford Site single-shell tanks (SSTs). In the laboratory, such mixtures can be made to undergo uncontrolled or explosive reactions by heating dry reagents to over 200 degrees C. In 1987, an Environmental Impact Statement (EIS), published by the U.S. Department of Energy (DOE), Final Environmental Impact Statement, Disposal of Hanford Defense High-Level Transuranic and Tank Waste, Hanford Site, Richland, Washington, included an environmental impact analysis of potential explosions involving ferrocyanide-nitrate mixtures. The EIS postulated that an explosion could occur during mechanical retrieval of saltcake or sludge from a ferrocyanide waste tank, and concluded that this worst-case accident could create enough energy to release radioactive material to the atmosphere through ventilation openings, exposing persons offsite to a short-term radiation dose of approximately 200 mrem. Later, in a separate study (1990), the General Accounting Office postulated a worst-case accident of one to two orders of magnitude greater than that postulated in the DOE EIS. The uncertainties regarding the safety envelope of the Hanford Site ferrocyanide waste tanks led to the declaration of the Ferrocyanide Unreviewed Safety Question (USQ) in October 1990

EL3 reactor description and safety analysis report; Pile EL3, rapport descriptif et de surete

Energy Technology Data Exchange (ETDEWEB)

NONE

1969-02-01

The EL-3 reactor is an experimental pile. Heterogenous type reactor, water moderated and cooled it uses slightly enriched uranium oxide as fuel (4.5 percent) distributed in vertical cells that constitute the core (the maximum number of cells is 99). It is conceived to function at a maximal thermal power of 20 MW. It supplies a maximum thermal neutron flux of 10{sup 14} neutrons/cm{sup 2}/sec. It has several experimental devices. The EL-3 reactor is surrounded by auxiliary circuits of fluids, in a sealed containment, slightly depressed. The primary heavy water coolant circuit is completely included in this containment. Its cooling is made by the intermediary of a light water secondary circuit by atmospheric refrigerants. The ventilation circuits of the sealed containment and the reactor block do not release air outside, under nornal functioning, by a particularly studied chimney only after filtering and eventually dilution. The eventual contamination of the light water or air by active products is permanently monitored to allow the reactor shutdown and avoid the release in atmosphere of dangerous products. The EL-3 reactor, laying down in may 1955, has diverged in july 1957, made its first ascending in power in december 1957 and reached its complete power in april 1958. The positioning of actual fuel (snow crystal) was made during summer 1964. Reactor with an experimental aim, it is used for theoretical and technological studies by material irradiation in the experimental channels and the core cells, with possibilities to constitute independent loops (relative to the cooling fluids). Thirty vertical channels are devoted to the fabrication of artificial radioelements. [French] La pile EL-3 est une pile experimentale. Du type heterogene, moderee et refroidie a l'eau lourde elle utilise comme combustible de l'oxygene d'uranium faiblement enrichi (4,5 p.cent) reparti en cellules verticales qui constituent le coeur (le nombre maximal de cellules est de, 99). Elle est

EL3 reactor description and safety analysis report; Pile EL3, rapport descriptif et de surete

Energy Technology Data Exchange (ETDEWEB)

NONE

1969-02-01

The EL-3 reactor is an experimental pile. Heterogenous type reactor, water moderated and cooled it uses slightly enriched uranium oxide as fuel (4.5 percent) distributed in vertical cells that constitute the core (the maximum number of cells is 99). It is conceived to function at a maximal thermal power of 20 MW. It supplies a maximum thermal neutron flux of 10{sup 14} neutrons/cm{sup 2}/sec. It has several experimental devices. The EL-3 reactor is surrounded by auxiliary circuits of fluids, in a sealed containment, slightly depressed. The primary heavy water coolant circuit is completely included in this containment. Its cooling is made by the intermediary of a light water secondary circuit by atmospheric refrigerants. The ventilation circuits of the sealed containment and the reactor block do not release air outside, under nornal functioning, by a particularly studied chimney only after filtering and eventually dilution. The eventual contamination of the light water or air by active products is permanently monitored to allow the reactor shutdown and avoid the release in atmosphere of dangerous products. The EL-3 reactor, laying down in may 1955, has diverged in july 1957, made its first ascending in power in december 1957 and reached its complete power in april 1958. The positioning of actual fuel (snow crystal) was made during summer 1964. Reactor with an experimental aim, it is used for theoretical and technological studies by material irradiation in the experimental channels and the core cells, with possibilities to constitute independent loops (relative to the cooling fluids). Thirty vertical channels are devoted to the fabrication of artificial radioelements. [French] La pile EL-3 est une pile experimentale. Du type heterogene, moderee et refroidie a l'eau lourde elle utilise comme combustible de l'oxygene d'uranium faiblement enrichi (4,5 p.cent) reparti en cellules verticales qui constituent le coeur (le nombre maximal de cellules est de, 99

Calculational study for criticality safety data of fissionable actinides

International Nuclear Information System (INIS)

Nojiri, Ichiro; Fukasaku, Yasuhiro.

1997-01-01

This study has been carried out to obtain basic criticality safety characteristics of minor actinides nuclides. Criticality safety data of minor actinides nuclides have been surveyed through public literatures. Critical mass of seven nuclides, Np-237, Am-241, Am-242m, Am-243, Cm-243, Cm-244 and Cm-245, have been calculated by using two code systems of criticality safety analysis, SCALE-4 and MCNP4A, under some material and reflector conditions. Some applicable cross-section libraries have been used for each code systems. Calculated data have been compared with each other and with published data. The results of this comparison shows that there is no discrepancy within the computational codes and the calculated data is strongly depend on the cross-section library. (author)

Safety training parks – A case study on the effectiveness of the trainings

DEFF Research Database (Denmark)

Räsänen, Tuula; Sormunen, E.; Reiman, Arto

The Safety Training Park (STP) concept is a unique Finnish safety training innovation. The STP provides different actors of the construction industry and other branches a practical occupational safety and health (OSH) training area. To the authors’ knowledge, no such parks exist in Europe besides...... Finland. Objec-tive was to study the effectiveness of the STP trainings at a large case company which participated in this study and which has actively trained its personnel in the park. The study was conducted from February 2015 to Feb-ruary 2017. Several key success factors were identified...... in the interviews of this case study. In addition, the company OSH statistics (2010 – 2016) showed a positive development at safety level. However, The Nordic Safety Climate Questionnaire did not show any significant change of results in a one year period. According to the results of the group interviews...

Combined evaluation. Plutonium transports in France. Problems of safety and reliability of transport container FS47; Evaluation Conjointe. Transports de plutonium en France. Problemes de surete et de securite du container de transport FS47

Energy Technology Data Exchange (ETDEWEB)

Marignac, Y.; Coeytaux, X. [Wise-Paris, 75 (France); Large, J.H. [Nuclear Engineer, Large and Associates, Londres (United Kingdom)

2004-09-15

This report concerns the safety and the protection of plutonium dioxide transported from Cogema La Hague to the mixed oxide fuel plant of Marcoule and Cadarache. The French approach of the transport safety is based on the combining of two essential principles: the first one affirms that the performances of the FS47 container in regard of containment (norms TS-R-1 from IAEA for the accidental conditions) is conceived to resist in any situation even terrorism or sabotage. In fact, the IAEA norm follows a probabilistic study without a voluntary attack such a terrorist one. The second principle rests on the ability to prevent the treat of terrorism acts, because of a secrecy policy on the plutonium transport. It appeared that the Green peace association has succeeded several times to know exactly the hours, the trips of the plutonium transport and this simple thing raises more questions than it solves. (N.C.)

Studying Patient Safety Culture from the Viewpoint of Nurse in educational hospitals Ilam City

Directory of Open Access Journals (Sweden)

Milad Borji

2016-12-01

Full Text Available Introduction: Patient safety culture is the first necessary step to reduce medical errors and improve patient's condition. In this context, this article aims at studying the condition of patient safety culture in hospitals in Elam in 2016. Materials and Methods: In this cross-sectional study, 150 nurses in Ilam were randomly selected. The Culture Hospital Survey on Patient Safety (HSOPSC was used and its reliability and validity had been confirmed by the previous studies. The data were analyzed by SPSS17. Results: The results showed that the nurses' safety was at positive(62.37± 8.70 and there could be found no significant difference in patient safety among the studied hospitals in this article (P<.05. Extra-organizational teamwork and non-punitive response, among the aspects of patient safety, had the lowest means and organizational learning and general understanding had the highest. Conclusion: Considering the importance of patient safety, the interventions need to be performed in order to improve the patient safety condition among nurses, especially in two aspects of extra-organizational teamwork and non-punitive response that had the lowest means.

Overview of the reactor safety study consequence model

International Nuclear Information System (INIS)

Wall, I.B.; Yaniv, S.S.; Blond, R.M.; McGrath, P.E.; Church, H.W.; Wayland, J.R.

1977-01-01

The Reactor Safety Study (WASH-1400) is a comprehensive assessment of the potential risk to the public from accidents in light water power reactors. The engineering analysis of the plants is described in detail in the Reactor Safety Study: it provides an estimate of the probability versus magnitude of the release of radioactive material. The consequence model, which is the subject of this paper, describes the progression of the postulated accident after the release of the radioactive material from the containment. A brief discussion of the manner in which the consequence calculations are performed is presented. The emphasis in the description is on the models and data that differ significantly from those previously used for these types of assessments. The results of the risk calculations for 100 light water power reactors are summarized

Cabri - water loop a new IPSN-OECD international research program

International Nuclear Information System (INIS)

Anon.

2001-01-01

In 1993, the Institut de Protection et de Surete Nucleaire (IPSN, the French Nuclear Safety and Radiation Protection Institute) working with EDF (electric utilities) and backed by the NRC (Nuclear Regulatory Commission, USA) launched a research program, dubbed Cabri REP Na addressing uranium oxide-based fuels and MOX fuels. So far twelve tests have been conducted including eight on UO 2 fuel and four on MOX fuel. More testing is now required to determine fuel performance at higher specific burn-up levels in typical PWR (Pressurized Water Reactor) conditions, the purpose being to determine the acceptance criteria for tomorrow's fuels. IPSN has defined a new research program for the Cabri reactor. The OECD's Nuclear Energy Agency is quarterbacking the international program called 'Cabri-Water Loop'. (authors)

Nuclear safety

International Nuclear Information System (INIS)

Tarride, Bruno

2015-10-01

The author proposes an overview of methods and concepts used in the nuclear industry, at the design level as well as at the exploitation level, to ensure an acceptable safety level, notably in the case of nuclear reactors. He first addresses the general objectives of nuclear safety and the notion of acceptable risk: definition and organisation of nuclear safety (relationships between safety authorities and operators), notion of acceptable risk, deterministic safety approach and main safety principles (safety functions and confinement barriers, concept of defence in depth). Then, the author addresses the safety approach at the design level: studies of operational situations, studies of internal and external aggressions, safety report, design principles for important-for-safety systems (failure criterion, redundancy, failure prevention, safety classification). The next part addresses safety during exploitation and general exploitation rules: definition of the operation domain and of its limits, periodic controls and tests, management in case of incidents, accidents or aggressions

Environmental Regulation and Food Safety: Studies of Protection ...

International Development Research Centre (IDRC) Digital Library (Canada)

2006-01-01

Jan 1, 2006 ... Book cover Environmental Regulation and Food Safety: Studies of ... are sometimes perceived in developing countries as nontariff barriers to trade. ... In some cases, products that had initially been refused access to a ...

Non-clinical models: validation, study design and statistical consideration in safety pharmacology.

Science.gov (United States)

Pugsley, M K; Towart, R; Authier, S; Gallacher, D J; Curtis, M J

2010-01-01

The current issue of the Journal of Pharmacological and Toxicological Methods (JPTM) focuses exclusively on safety pharmacology methods. This is the 7th year the Journal has published on this topic. Methods and models that specifically relate to methods relating to the assessment of the safety profile of a new chemical entity (NCE) prior to first in human (FIH) studies are described. Since the Journal started publishing on this topic there has been a major effort by safety pharmacologists, toxicologists and regulatory scientists within Industry (both large and small Pharma as well as Biotechnology companies) and also from Contract Research Organizations (CRO) to publish the surgical details of the non-clinical methods utilized but also provide important details related to standard and non-standard (or integrated) study models and designs. These details from core battery and secondary (or ancillary) drug safety assessment methods used in drug development programs have been the focus of these special issues and have been an attempt to provide validation of methods. Similarly, the safety pharmacology issues of the Journal provide the most relevant forum for scientists to present novel and modified methods with direct applicability to determination of drug safety-directly to the safety pharmacology scientific community. The content of the manuscripts in this issue includes the introduction of additional important surgical methods, novel data capture and data analysis methods, improved study design and effects of positive control compounds with known activity in the model. Copyright 2010 Elsevier Inc. All rights reserved.

Alberta Environment's weir safety program : options for rehabilitation to improve public safety : a case study of the Calgary weir

Energy Technology Data Exchange (ETDEWEB)

Blakely, D [Alberta Environment, Edmonton, AB (Canada)

2009-07-01

Alberta Environment Water Management Operations (WMO) owns and operates 46 dams and 800 kilometres of canals in Alberta. The WMO consists of 120 staff and several contract operators to take care of this infrastructure. Most of the infrastructure supplies water for irrigation use, which adds 5 billion dollars to the provincial economy annually. Other water uses include stock watering, domestic use, municipal use, recreational use and habitat. Alberta Environment's weir safety program was also discussed along with options for rehabilitation to improve public safety. A case study of Calgary's Weir Dam on the Bow River was highlighted. A brief history of the dam was offered and safety programs around provincially-owned weirs were discussed. Photographs were included to illustrate some of the additional safety measures at the Calgary weir, such as suspended safety buoys upstream of the boom directing paddlers to the portage trail, and signage on the river that can be activated when the boom is out. Typical river users on the Calgary Bow River and safety history at the Calgary Weir were discussed along with other topics such as the Calgary Bow River weir project criteria; project design progress; pre-feasibility options; scale modelling; final design analysis; construction funding; and proposed changes to the safety program for the new weir configuration. figs.

Research study about the establishment of safety culture. Effects of organizational factors in construction industry's safety indices

International Nuclear Information System (INIS)

Kojima, Mitsuhiro; Hirose, Humiko; Takano, Kenichi; Hasegawa, Naoko

1999-01-01

To find the relationships between safety related activities (such as safety patrol' or '4s/5s activities') and accidents rate in the workplace, questionnaires were sent to 965 construction companies and 120 answers were returned. In this questionnaire, safety activities, safety regulations and safety policies of the companies were asked and organizational climates, company policies, philosophies and the number of accidents in workplace were also asked. There seems some relationships between accidents rate and safety activities, safety regulations and safety policies in the companies, but the deviations between estimate values and observed values are so great that it seems impossible to estimate the accidents rate in the working place from the safety activities, safety regulations and safety policies of the companies. On the other hand, some characteristics of safety activities and organizational climates in the construction industry were identified using multi variants analysis. More detailed researches using sophisticated questionnaire will be conducted in the construction industry and petrochemical industry and relationships between the accidents rate and the safety activities will be compared between different industries. (author)

Safety-related topics from the Nuclear Power Options Viability Study

International Nuclear Information System (INIS)

Trauger, D.B.; White, J.D.

1986-01-01

The Nuclear Power Options Viability Study (NPOVS) evaluated innovative reactor concepts, and this article reviews NPOVS findings, with emphasis on safety and licensing. The reactors studied were of light-water, liquid-metal, and helium-cooled concepts, and most were of modular design. Prelicensed standard plants offer an important step toward regulatory stability and early licensing approvals with public participation before major expenditures. Advanced reactors with passive safety features offer the possibility of performance-based regulation. The concepts studied appear to be potentially viable, but more complete designs will be required before economic evaluations can be definitive

A Study on Drug Safety Monitoring Program in India

Science.gov (United States)

Ahmad, A.; Patel, Isha; Sanyal, Sudeepa; Balkrishnan, R.; Mohanta, G. P.

2014-01-01

Pharmacovigilance is useful in assuring the safety of medicines and protecting the consumers from their harmful effects. A number of single drugs as well as fixed dose combinations have been banned from manufacturing, marketing and distribution in India. An important issue about the availability of banned drugs over the counter in India is that sufficient adverse drug reactions data about these drugs have not been reported. The most common categories of drugs withdrawn in the last decade were nonsteroidal antiinflammatory drugs (28%), antidiabetics (14.28%), antiobesity (14.28%), antihistamines (14.28%), gastroprokinetic drugs (7.14%), breast cancer and infertility drugs (7.14%), irritable bowel syndrome and constipation drugs (7.14%) and antibiotics (7.14%). Drug withdrawals from market were made mainly due to safety issues involving cardiovascular events (57.14%) and liver damage (14.28%). Majority of drugs have been banned since 3-5 years in other countries but are still available for sale in India. The present study compares the drug safety monitoring systems in the developed countries such as the USA and UK and provides implications for developing a system that can ensure the safety and efficacy of drugs in India. Absence of a gold standard for a drug safety surveillance system, variations in culture and clinical practice across countries makes it difficult for India to completely adopt another country's practices. There should be a multidisciplinary approach towards drug safety that should be implemented throughout the entire duration spanning from drug discovery to usage by consumers. PMID:25425751

Studying the Relationship between Individual and Organizational Factors and Nurses' Perception of Patient Safety Culture

Directory of Open Access Journals (Sweden)

Farahnaz Abdolahzadeh

2012-11-01

Full Text Available Introduction: Safety culture is considered as an important factor in improving patient safety. Therefore, identifying individual and organizational factors affecting safety culture is crucial. This study was carried out to determine individual and organizational factors associated with nurses' perception of patient safety culture. Methods: The present descriptive study included 940 nurses working in four training hospitals affiliated with Urmia University of Medical Sciences (Iran. Data was collected through the self-report questionnaire of patient safety culture. Descriptive (number, percent, mean, and standard deviation and inferential (t-test and analysis of variance statistics were used to analyze the data in SPSS. Results: Nurses' perception of patient safety culture was significantly correlated with marital status, workplace, and overtime hours. Conclusion: The results of this study revealed that some individual and organizational factors can impact on nurses' perception of patient safety culture. Nursing authorities should thus pay more attention to factors which promote patient safety culture and ultimately the safety of provided services.

Example of a SWOV (Institute for Road Safety Research) safety study : "Avenida Marginal", Lisbon 1989.

NARCIS (Netherlands)

Janssen, S.T.M.C.

1991-01-01

This paper describes the accident study on the Marginal Road between Alges and Cascais in Portugal. The aim of this study was to produce a philosophy for a strategy to select the best safety measures out of several which had already been proposed. The general point of departure in this philosophy is

Assessment of Safety Condition in One of the Teaching Hospitals in Kermanshah (2015: A Case Study

Directory of Open Access Journals (Sweden)

Masod Ghanbari Kakavand

2016-09-01

Full Text Available Background & Aims of the Study: Many working conditions-related stress factors that can produce injuries and illnesses are important in hospital environments. So, the health and safety of nurses and patients from workplace-induced injuries and illnesses is important. In this study, we have assessed the safety condition of one of the teaching hospitals in Kermanshah (2015. Materials and Methods: This descriptive and cross-sectional study was conducted in one of the teaching hospital of Kermanshah University of medical sciences. For this aim a checklist was prepared based on the Occupational Safety and Health Administration's standards and Part 3 of the manual of National Building Regulations. These checklists comprised (The final checklist had 239 questions of 9 dimensions various sections of safety including; fire safety, building safety, electrical safety, emergency exit routes safety, heating and cooling equipment safety, operating room and laundry room and salty home safety. Eventually, using SPSS 16 and descriptive statistics, data were analyzed. Results: According to the results of this study, 66.6% of the units had poor safety and 33.4% of them were moderately safe. As well as, only ICU and CCU unit, heating and cooling equipment and operational room showed moderate compliance with safety requirements and other sections were poorly complied. Conclusion: The results of this study showed that safety conditions of hospital were not at favorable level. These poor safety statues can jeopardize patients and hospital personnel. Thus some interventions such as improvement of working conditions, compliance with safety acts and implementation of health, safety and environmental management system would be necessary.

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

NARCIS (Netherlands)

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

2012-01-01

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

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.

Study of system safety evaluation on LTO of national project. NISA safety research project on system safety of nuclear power plants

International Nuclear Information System (INIS)

Takizawa, Masayuki; Sekimura, Naoto; Miyano, Hiroshi; Aoyama, Katsunobu

2012-01-01

Japanese safety regulatory body, that is, Nuclear and Industrial Safety Agency (NISA) started a 5-year national safety research project as 'the first stage' from 2006 FY to 2010 FY whose objective is 'Improve the technical information basis in order to utilize knowledge as well as information related to ageing management and maintenance of NPPs. Fukushima disaster happened in March 2011, and the priority of research needs for ageing management dramatically changed in Japan. The second-stage national project started in October 2011 with the concept of 'system safety' of NNPs where not only ageing management on degradation phenomena of important components but also safety management on total plant systems are paid attention to. The second-stage project is so called 'Japanese Ageing Management Program for System Safety (JAMPSS)'. (author)

Pressure Safety: Advanced Self-Study 30120

Energy Technology Data Exchange (ETDEWEB)

Glass, George [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-02-29

Pressure Safety Advance Self-Study (Course 30120) consists of an introduction, five modules, and a quiz. To receive credit in UTrain for completing this course, you must score 80% or better on the 15-question quiz (check UTrain). Directions for initiating the quiz are appended to the end of this training manual. This course contains several links to LANL websites. UTrain might not support active links, so please copy links into the address line in your browser.

A Quantitative Feasibility Study on Potential Safety Improvement Effects of Advanced Safety Features in APR-1400 when Applied to OPR-1000

Energy Technology Data Exchange (ETDEWEB)

Ualikhan Zhiyenbayev [KAIST, Daejeon (Korea, Republic of); Chung, Dae Wook [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2015-10-15

This study aims to test the feasibility of the applications using Probabilistic Safety Assessment (PSA). Particularly, three of those advanced safety features are selected as follows: 1. Providing an additional Emergency Diesel Generator (EDG); 2. Increasing the capacity of Class 1E batteries; 3. Placing a Refueling Water Storage Tank (RWST) inside containment, i.e., change from RWST to IRWST. The Advanced Power Reactor 1400 (APR-1400) adopts several advanced safety features compared to its predecessor, the Optimized Power Reactor 1000 (OPR-1000), which includes an additional Emergency Diesel Generator, increase in battery capacity, in-containment refueling water storage tank (IRWST), and so on. Considering the remarkable advantages of these safety features in safety improvement and the design similarities between APR-1400 and OPR-1000, it is feasible to apply key advanced safety features of APR-1400 to OPR-1000 to enhance the safety. The selected safety features are incorporated into OPR-1000 PSA model using the Advanced Information Management System (AIMS) for PSA and CDFs are re-evaluated for each application and combination of three applications. Based on current results, it is concluded that three of key advanced safety features of APR-1400 can be effectively applied to OPR-1000, resulting in considerable safety improvement. In aggregate, three advanced safety features, which are an additional EDG, increased battery capacity and IRWST, can reduce the CDF of OPR-1000 by more than 15% when applied altogether.

A Quantitative Feasibility Study on Potential Safety Improvement Effects of Advanced Safety Features in APR-1400 when Applied to OPR-1000

International Nuclear Information System (INIS)

Ualikhan Zhiyenbayev; Chung, Dae Wook

2015-01-01

This study aims to test the feasibility of the applications using Probabilistic Safety Assessment (PSA). Particularly, three of those advanced safety features are selected as follows: 1. Providing an additional Emergency Diesel Generator (EDG); 2. Increasing the capacity of Class 1E batteries; 3. Placing a Refueling Water Storage Tank (RWST) inside containment, i.e., change from RWST to IRWST. The Advanced Power Reactor 1400 (APR-1400) adopts several advanced safety features compared to its predecessor, the Optimized Power Reactor 1000 (OPR-1000), which includes an additional Emergency Diesel Generator, increase in battery capacity, in-containment refueling water storage tank (IRWST), and so on. Considering the remarkable advantages of these safety features in safety improvement and the design similarities between APR-1400 and OPR-1000, it is feasible to apply key advanced safety features of APR-1400 to OPR-1000 to enhance the safety. The selected safety features are incorporated into OPR-1000 PSA model using the Advanced Information Management System (AIMS) for PSA and CDFs are re-evaluated for each application and combination of three applications. Based on current results, it is concluded that three of key advanced safety features of APR-1400 can be effectively applied to OPR-1000, resulting in considerable safety improvement. In aggregate, three advanced safety features, which are an additional EDG, increased battery capacity and IRWST, can reduce the CDF of OPR-1000 by more than 15% when applied altogether

Safety culture assessment in petrochemical industry: a comparative study of two algerian plants.

Science.gov (United States)

Boughaba, Assia; Hassane, Chabane; Roukia, Ouddai

2014-06-01

To elucidate the relationship between safety culture maturity and safety performance of a particular company. To identify the factors that contribute to a safety culture, a survey questionnaire was created based mainly on the studies of Fernández-Muñiz et al. The survey was randomly distributed to 1000 employees of two oil companies and realized a rate of valid answer of 51%. Minitab 16 software was used and diverse tests, including the descriptive statistical analysis, factor analysis, reliability analysis, mean analysis, and correlation, were used for the analysis of data. Ten factors were extracted using the analysis of factor to represent safety culture and safety performance. The results of this study showed that the managers' commitment, training, incentives, communication, and employee involvement are the priority domains on which it is necessary to stress the effort of improvement, where they had all the descriptive average values lower than 3.0 at the level of Company B. Furthermore, the results also showed that the safety culture influences the safety performance of the company. Therefore, Company A with a good safety culture (the descriptive average values more than 4.0), is more successful than Company B in terms of accident rates. The comparison between the two petrochemical plants of the group Sonatrach confirms these results in which Company A, the managers of which are English and Norwegian, distinguishes itself by the maturity of their safety culture has significantly higher evaluations than the company B, who is constituted of Algerian staff, in terms of safety management practices and safety performance.

Report of Activity, 1997; Rapport d'activite, 1997

Energy Technology Data Exchange (ETDEWEB)

Lacoste, Andre-Claude; Livolant, Michel [eds.] [Inst. de Protection et de Surete Nucleaire, CEA Centre d' Etudes de Fontenay-aux-Roses, 92 (France)

1998-07-01

The Institute of Nuclear Protection and Safety (Institut de Protection et de Surete Nucleaire) - IPSN carries out research and expert studies needed in managing nuclear risk and consequences of nuclear events on population and environment, i.e. supervises the safety of installations, the prevention and study of accidents, the human health and environmental conditions, the safety of transport and has also the task of organizing the management of the crisis situations. IPSN has the mission of informing the public and participates in numerous international actions. Thus, since 1989 IPSN and its German counterpart, GRS, co-operate towards improving of the nuclear safety in Europe and developing a common approach of international issues. As acting for public authorities (government departments in charge with industry, environment, health or labor), IPSN grants technical authorizations on request of DSIN exploiters. The IPSN personnel amounts up to 1300 employees of whom around two thirds are engineers, researchers, physicians, agronomists, and veterinarians. This IPSN annual report contains in the 'Free Tribune' section two general papers entitled: 'The federalist role of research at IPSN' by Catherine Lecompte and 'The dose, a central issue in radioprotection debates' by Annie Sugier. Then five sub-reports follow: 1.The safety of nuclear facilities and radioactive wastes; 2.Crisis management; 3. The management of sensitive materials (protection and control of sensitive materials and safety analysis of the radioactive materials transport); 4.Protection of human health; 5.Environment protection. The report also presents the international activities, the cooperation IPSN/GRS, the budget, the staff and the human resource policy and the communication activity.

Key aspects in managing safety when working with multiple contractors: A case study

NARCIS (Netherlands)

Drupsteen, L.; Rasmussen, H.B.; Ustailieva, E.; Kampen, J. van

2015-01-01

Working with multiple contractors in a shared workplace can introduce and increase safety risks due to complexity. The aim of this study was to explore how safety issues are recognized in a specific case and to identify whether clients and contractors perceive problems similarly. The safety issues

System and safety studies of accelerator driven systems for transmutation. Annual report 2007

International Nuclear Information System (INIS)

Arzhanov, Vasily; Fokau, Andrei; Persson, Calle; Runevall, Odd; Sandberg, Nils; Tesinsky, Milan; Wallenius, Janne; Youpeng Zhang

2008-05-01

Within the project 'System and safety studies of accelerator driven systems for transmutation', research on design and safety of sub-critical reactors for recycling of minor actinides is performed. During 2007, the reactor physics division at KTH has calculated safety parameters for EFIT-400 with cermet fuel, permitting to start the transient safety analysis. The accuracy of different reactivity meters applied to the YALINA facility was assessed and neutron detection studies were performed. A model to address deviations from point kinetic behaviour was developed. Studies of basic radiation damage physics included calculations of vacancy formation and activation enthalpies in bcc niobium. In order to predict the oxygen potential of inert matrix fuels, a thermo-chemical model for mixed actinide oxides was implemented in a phase equilibrium code

International technical assistance example. Consortium action in Bulgaria

International Nuclear Information System (INIS)

Mattei, J.M.; Milhem, J.L.

1993-03-01

The safety status achieved last year at the Kozloduy Nuclear Power Plant (NPP) and the capability of the Bulgarian Nuclear Safety Authority (BNSA) to assess the safety of the plant and the adequacy of proposed improvements have been matters of international concern. However, the Kozloduy NPP contributes 35-40 per cent of the electrical generating capacity in Bulgaria. For further operation of the plants, it is therefore, essential that safety is improved. In july 1991, the Commission of the European Communities (CEC) instituted a Six Months Emergency Action Programme for Bulgaria under the PHARE regional nuclear safety programme. The programme consisted of three parts: - an industrial emergency programme supporting the utility of the Kozloduy NPP, - a study to evaluate Bulgaria's electricity needs, - technical assistance for reinforcement of the Bulgarian Nuclear Safety Authority. For the third part, complementary to the industrial emergency programme carried out by the WANO (World Association of Nuclear Operators), a Consortium of expert institutions and regulatory from EC member states was established by CEC for assistance to BNSA. The Consortium consisted of: - Institut de Protection et de Surete Nucleaire (IPSN), France, technical support of the French regulatory body, - Gesellschaft fur Anlagen und Reaktorsicherheit (GRS) mbH, Germany, an organization in safety engineering, technical support of governmental regulatory body, - AIB-Vincotte Nuclear (AVN), Belgium, the organization authorized by the Belgian Government for licensing and inspection of nuclear power plants, - UK Atomic Energy Authority (AEA Technology), an independent UK Government owned nuclear R and D and consultancy organization, - Nuclear Installations Inspectorate (NII) of the Health and Safety Executive, United Kingdom, the nuclear regulatory body for the United Kingdom

International technical assistance example. Consortium action in Bulgaria; Exemple d`assistance internationale. Cas de la Bulgarie, action du consortium

Energy Technology Data Exchange (ETDEWEB)

Mattei, J M; Milhem, J L [CEA Centre d` Etudes de Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire; Heuser, F W; Kelm, P [Gesellschaft fuer Reaktorsicherheit mbH (GRS), Koeln (Germany)

1993-03-01

The safety status achieved last year at the Kozloduy Nuclear Power Plant (NPP) and the capability of the Bulgarian Nuclear Safety Authority (BNSA) to assess the safety of the plant and the adequacy of proposed improvements have been matters of international concern. However, the Kozloduy NPP contributes 35-40 per cent of the electrical generating capacity in Bulgaria. For further operation of the plants, it is therefore, essential that safety is improved. In july 1991, the Commission of the European Communities (CEC) instituted a Six Months Emergency Action Programme for Bulgaria under the PHARE regional nuclear safety programme. The programme consisted of three parts: - an industrial emergency programme supporting the utility of the Kozloduy NPP, - a study to evaluate Bulgaria`s electricity needs, - technical assistance for reinforcement of the Bulgarian Nuclear Safety Authority. For the third part, complementary to the industrial emergency programme carried out by the WANO (World Association of Nuclear Operators), a Consortium of expert institutions and regulatory from EC member states was established by CEC for assistance to BNSA. The Consortium consisted of: - Institut de Protection et de Surete Nucleaire (IPSN), France, technical support of the French regulatory body, - Gesellschaft fur Anlagen und Reaktorsicherheit (GRS) mbH, Germany, an organization in safety engineering, technical support of governmental regulatory body, - AIB-Vincotte Nuclear (AVN), Belgium, the organization authorized by the Belgian Government for licensing and inspection of nuclear power plants, - UK Atomic Energy Authority (AEA Technology), an independent UK Government owned nuclear R and D and consultancy organization, - Nuclear Installations Inspectorate (NII) of the Health and Safety Executive, United Kingdom, the nuclear regulatory body for the United Kingdom.

Consumer food handling in the home: a review of food safety studies.

Science.gov (United States)

Redmond, Elizabeth C; Griffith, Christopher J

2003-01-01

Epidemiological data from Europe, North America, Australia, and New Zealand indicate that a substantial proportion of foodborne disease is attributable to improper food preparation practices in consumers' homes. International concern about consumer food safety has prompted considerable research to evaluate domestic food-handling practices. The majority of consumer food safety studies in the last decade have been conducted in the United Kingdom and Northern Ireland (48%) and in the United States (42%). Surveys (questionnaires and interviews), the most frequent means of data collection, were used in 75% of the reviewed studies. Focus groups and observational studies have also been used. One consumer food safety study examined the relationship between pathogenic microbial contamination from raw chicken and observed food-handling behaviors, and the results of this study indicated extensive Campylobacter cross-contamination during food preparation sessions. Limited information about consumers' attitudes and intentions with regard to safe food-handling behaviors has been obtained, although a substantial amount of information about consumer knowledge and self-reported practices is available. Observation studies suggest that substantial numbers of consumers frequently implement unsafe food-handling practices. Knowledge, attitudes, intentions, and self-reported practices did not correspond to observed behaviors, suggesting that observational studies provide a more realistic indication of the food hygiene actions actually used in domestic food preparation. An improvement in consumer food-handling behavior is likely to reduce the risk and incidence of foodborne disease. The need for the development and implementation of food safety education strategies to improve specific food safety behaviors is reviewed in this paper.

The safety designs for the TITAN reversed-field pinch reactor study

International Nuclear Information System (INIS)

Wong, C.P.C.; Cheng, E.T.; Creedon, R.L.; Hoot, C.G.; Schultz, K.R.; Grotz, S.P.; Blanchard, J.; Sharafat, S.; Najmabadi, F.

1989-01-01

TITAN is a study to investigate the potential of the reversed-field pinch concept as a compact, high-power density energy system. Two reactor concepts were developed, a self-cooled lithium design with vanadium structure and an aqueous solution loop-in-pool design, both operating at 18 MW/m 2 . The key safety features of the TITAN-I lithium-vanadium blanket design are in material selection, fusion power core configuration selection, lithium piping connections, and passive lithium drain tank system. Based on these safety features and results from accident evaluation, TITAN-I can at least be rated at a level 3 of safety assurance. For the TITAN-II aqueous loop-in-pool design, the key passive feature is the complete submersion of the fusion power core and the corresponding primary coolant loop system into a pool of low temperature water. Based on this key safety design feature, the TITAN-II design can be rated at a level 2 of safety assurance. (orig.)

A study on quantitative V and V of safety-critical software

International Nuclear Information System (INIS)

Eom, H. S.; Kang, H. G.; Chang, S. C.; Ha, J. J.; Son, H. S.

2004-03-01

Recently practical needs have required quantitative features for the software reliability for Probabilistic Safety Assessment which is one of the important methods being used in assessing the overall safety of nuclear power plant. But the conventional assessment methods of software reliability could not provide enough information for PSA of NPP, therefore current assessments of a digital system which includes safety-critical software usually exclude the software part or use arbitrary values. This paper describes a Bayesian Belief Networks based method that models the rule-based qualitative software assessment method for a practical use and can produce quantitative results for PSA. The framework was constructed by utilizing BBN that can combine the qualitative and quantitative evidence relevant to the reliability of safety-critical software and can infer a conclusion in a formal and a quantitative way. The case study was performed by applying the method for assessing the quality of software requirement specification of safety-critical software that will be embedded in reactor protection system

The safety designs for the TITAN reversed-field pinch reactor study

International Nuclear Information System (INIS)

Wong, C.P.C.; Cheng, E.T.; Creedon, R.L.; Hoot, C.G.; Schultz, K.R.; Grotz, S.P.; Blanchard, J.P.; Sharafat, S.; Najmabadi, F.

1988-01-01

TITAN is a study to investigate the potential of the reversed-field pinch concept as a compact, high-power density energy system. Two reactor concepts were developed, a self-cooled lithium design with vanadium structure and an aqueous solution loop-in-pool design, both operating at 18 MW/m 2 . The key safety features of the TITAN-I lithium-vanadium blanket design are in material selection, fusion power core configuration selection, lithium piping connections and passive lithium drain tank system. Based on these safety features and results from accident evaluation, TITAN-I can at least be rated as level 3 of safety assurance. For the TITAN-II aqueous loop-in-pool design, the key passive feature is the complete submersion of the fusion power core and the corresponding primary coolant loop system into a pool of low temperature water. Based on this key safety design feature, the TITAN-II design can be rated as level 2 of safety assurance. 7 refs., 2 figs

A study for safety and health management problem of semiconductor industry in Taiwan.

Science.gov (United States)

Chao, Chin-Jung; Wang, Hui-Ming; Feng, Wen-Yang; Tseng, Feng-Yi

2008-12-01

The main purpose of this study is to discuss and explore the safety and health management in semiconductor industry. The researcher practically investigates and interviews the input, process and output of the safety and health management of semiconductor industry by using the questionnaires and the interview method which is developed according to the framework of the OHSAS 18001. The result shows that there are six important factors for the safety and health management in Taiwan semiconductor industry. 1. The company should make employee clearly understand the safety and health laws and standards. 2. The company should make the safety and health management policy known to the public. 3. The company should put emphasis on the pursuance of the safety and health management laws. 4. The company should prevent the accidents. 5. The safety and health message should be communicated sufficiently. 6. The company should consider safety and health norm completely.

System and safety studies of accelerator driven systems for transmutation. Annual report 2007

Energy Technology Data Exchange (ETDEWEB)

Arzhanov, Vasily; Fokau, Andrei; Persson, Calle; Runevall, Odd; Sandberg, Nils; Tesinsky, Milan; Wallenius, Janne; Youpeng Zhang (Div. of Reactor Physics, Royal Institute of Technology, Stockholm (Sweden))

2008-05-15

Within the project 'System and safety studies of accelerator driven systems for transmutation', research on design and safety of sub-critical reactors for recycling of minor actinides is performed. During 2007, the reactor physics division at KTH has calculated safety parameters for EFIT-400 with cermet fuel, permitting to start the transient safety analysis. The accuracy of different reactivity meters applied to the YALINA facility was assessed and neutron detection studies were performed. A model to address deviations from point kinetic behaviour was developed. Studies of basic radiation damage physics included calculations of vacancy formation and activation enthalpies in bcc niobium. In order to predict the oxygen potential of inert matrix fuels, a thermo-chemical model for mixed actinide oxides was implemented in a phase equilibrium code

The impact of masculinity on safety oversights, safety priority and safety violations in two male-dominated occupations

DEFF Research Database (Denmark)

Nielsen, Kent; Hansen, Claus D.; Bloksgaard, Lotte

2015-01-01

Background Although men have a higher risk of occupational injuries than women the role of masculinity for organizational safety outcomes has only rarely been the object of research. Aim The current study investigated the association between masculinity and safety oversights, safety priority......-related context factors (safety leadership, commitment of the safety representative, and safety involvement) and three safety-related outcome factors (safety violations, safety oversights and safety priority) were administered twice 12 months apart to Danish ambulance workers (n = 1157) and slaughterhouse workers...

Survey of the state of the German safety study

International Nuclear Information System (INIS)

Heuser, F.W.; Kotthoff, K.

1977-01-01

In spring 1976 the Federal Ministry of Research and Technology has ordered a safety study to assess the risk for a nuclear power plant with a PWR. Giving first a survey on the main subtasks of the study the present state of work and some first results are discussed. Assuming a failure of safety systems a core melt event and a subsequent failure of the containment could occur. Corresponding accident sequences are discussed in some detail. Related hereto the results of some calculations for fission product release with respect to different containment failure modes are given. According to the results obtained so far the consequences of a core melt event can essentially be restricted by the retention function of the containment. (orig.) [de

Nuclear Criticality Technology and Safety Project parameter study database

International Nuclear Information System (INIS)

Toffer, H.; Erickson, D.G.; Samuel, T.J.; Pearson, J.S.

1993-03-01

A computerized, knowledge-screened, comprehensive database of the nuclear criticality safety documentation has been assembled as part of the Nuclear Criticality Technology and Safety (NCTS) Project. The database is focused on nuclear criticality parameter studies. The database has been computerized using dBASE III Plus and can be used on a personal computer or a workstation. More than 1300 documents have been reviewed by nuclear criticality specialists over the last 5 years to produce over 800 database entries. Nuclear criticality specialists will be able to access the database and retrieve information about topical parameter studies, authors, and chronology. The database places the accumulated knowledge in the nuclear criticality area over the last 50 years at the fingertips of a criticality analyst

Perceived organizational support for safety and employee safety voice: the mediating role of coworker support for safety.

Science.gov (United States)

Tucker, Sean; Chmiel, Nik; Turner, Nick; Hershcovis, M Sandy; Stride, Chris B

2008-10-01

In the present study, we modeled 2 sources of safety support (perceived organizational support for safety and perceived coworker support for safety) as predictors of employee safety voice, that is, speaking out in an attempt to change unsafe working conditions. Drawing on social exchange and social impact theories, we hypothesized and tested a mediated model predicting employee safety voice using a cross-sectional survey of urban bus drivers (n = 213) in the United Kingdom. Hierarchical regression analysis showed that perceived coworker support for safety fully mediated the relationship between perceived organizational support for safety and employee safety voice. This study adds to the employee voice literature by evaluating the important role that coworkers can play in encouraging others to speak out about safety issues. Implications for research and practice related to change-oriented safety communication are discussed.

Safety in home care: A research protocol for studying medication management

Directory of Open Access Journals (Sweden)

Easty Anthony

2010-06-01

Full Text Available Abstract Background Patient safety is an ongoing global priority, with medication safety considered a prevalent, high-risk area of concern. Yet, we have little understanding of the supports and barriers to safe medication management in the Canadian home care environment. There is a clear need to engage the providers and recipients of care in studying and improving medication safety with collaborative approaches to exploring the nature and safety of medication management in home care. Methods A socio-ecological perspective on health and health systems drives our iterative qualitative study on medication safety with elderly home care clients, family members and other informal caregivers, and home care providers. As we purposively sample across four Canadian provinces: Alberta (AB, Ontario (ON, Quebec (QC and Nova Scotia (NS, we will collect textual and visual data through home-based interviews, participant-led photo walkabouts of the home, and photo elicitation sessions at clients' kitchen tables. Using successive rounds of interpretive description and human factors engineering analyses, we will generate robust descriptions of managing medication at home within each provincial sample and across the four-province group. We will validate our initial interpretations through photo elicitation focus groups with home care providers in each province to develop a refined description of the phenomenon that can inform future decision-making, quality improvement efforts, and research. Discussion The application of interpretive and human factors lenses to the visual and textual data is expected to yield findings that advance our understanding of the issues, challenges, and risk-mitigating strategies related to medication safety in home care. The images are powerful knowledge translation tools for sharing what we learn with participants, decision makers, other healthcare audiences, and the public. In addition, participants engage in knowledge exchange

Safety studies concerning nuclear power reactors

International Nuclear Information System (INIS)

Bailly, Jean; Pelce, Jacques

1980-01-01

The safety of nuclear installations poses different technical problems, whether concerning pressurized water reactors or fast reactors. But investigating methods are closely related and concern, on the one hand, the behavior of shields placed between fuel and outside and, on the other, analysis of accidents. The article is therefore in two parts based on the same plan. Concerning light water reactors, the programme of studies undertaken in France accounts for the research carried out in countries where collaboration agreements exist. Concerning fast reactors, France has the initiative of their studies owing to her technical advance, which explains the great importance of the programmes under way [fr

Immunogenicity of biologically-derived therapeutics: assessment and interpretation of nonclinical safety studies.

Science.gov (United States)

Ponce, Rafael; Abad, Leslie; Amaravadi, Lakshmi; Gelzleichter, Thomas; Gore, Elizabeth; Green, James; Gupta, Shalini; Herzyk, Danuta; Hurst, Christopher; Ivens, Inge A; Kawabata, Thomas; Maier, Curtis; Mounho, Barbara; Rup, Bonita; Shankar, Gopi; Smith, Holly; Thomas, Peter; Wierda, Dan

2009-07-01

An evaluation of potential antibody formation to biologic therapeutics during the course of nonclinical safety studies and its impact on the toxicity profile is expected under current regulatory guidance and is accepted standard practice. However, approaches for incorporating this information in the interpretation of nonclinical safety studies are not clearly established. Described here are the immunological basis of anti-drug antibody formation to biopharmaceuticals (immunogenicity) in laboratory animals, and approaches for generating and interpreting immunogenicity data from nonclinical safety studies of biotechnology-derived therapeutics to support their progression to clinical evaluation. We subscribe that immunogenicity testing strategies should be adapted to the specific needs of each therapeutic development program, and data generated from such analyses should be integrated with available clinical and anatomic pathology, pharmacokinetic, and pharmacodynamic data to properly interpret nonclinical studies.

Criticality safety (prospect of study in NUCEF)

International Nuclear Information System (INIS)

Itagaki, Masafumi

1996-01-01

Experimental studies of criticality safety are under way using STACY and TRACY in NUCEF. Collection of fundamental data on criticality in a solution system is undergoing with STACY to confirm that the likelihood of criticality safety in the system constructed on the assumption of apparatuses in a reprocessing plant is enough large. Whereas some experiments simulating criticality accidents in a reprocessing plant using TRACY were designed to investigate the behaviors of fuel solution and radioactive matters in order to clarify whether it is possible to safely shut them in the facility even if a critical accident occurs. Both STACY and TRACY reached the criticality in 1995. Up to now a series of criticality experiments have been done using STACY with a core tank φ60 cm and the first periodical examination is now under way. On the other hand, we have a plan using TRACY to investigate the behaviors of nuclear heat solution at a criticality accident, and the releasing, transfer and deposition of radioactive materials. After reaching the criticality for the first, the performance verification test has been conducted. The full-scale study using TRACY is planned to begin in the second half of 1996. (M.N.)

'BeSAFE', effect-evaluation of internet-based, tailored safety information combined with personal counselling on parents' child safety behaviours: study design of a randomized controlled trial

Directory of Open Access Journals (Sweden)

van Beeck Eduard F

2010-08-01

Full Text Available Abstract Background Injuries in or around the home are the most important cause of death among children aged 0-4 years old. It is also a major source of morbidity and loss of quality of life. In order to reduce the number of injuries, the Consumer Safety Institute introduced the use of Safety Information Leaflets in the Netherlands to provide safety education to parents of children aged 0-4 years. Despite current safety education, necessary safety behaviours are still not taken by a large number of parents, causing unnecessary risk of injury among young children. In an earlier study an E-health module with internet-based, tailored safety information was developed and applied. It concerns an advice for parents on safety behaviours in their homes regarding their child. The aim of this study is to evaluate the effect of this safety information combined with personal counselling on parents' child safety behaviours. Methods/Design Parents who are eligible for the regular well-child visit with their child at child age 5-8 months are invited to participate in this study. Participating parents are randomized into one of two groups: 1 internet-based, tailored safety information combined with personal counselling (intervention group, or 2 personal counselling using the Safety Information Leaflets of the Consumer Safety Institute in the Netherlands for children aged 12 to 24 months (control group. All parents receive safety information on safety topics regarding the prevention of falling, poisoning, drowning and burning. Parents of the intervention group will access the internet-based, tailored safety information module when their child is approximately 10 months old. After completion of the assessment questions, the program compiles a tailored safety advice. The parents are asked to devise and inscribe a personal implementation intention. During the next well-child visit, the Child Health Clinic professional will discuss this tailored safety information

Organic chemistry and radiochemistry: study of chemical interactions between iodine and paint of French nuclear reactor in a severe accident situation

International Nuclear Information System (INIS)

Aujollet, Y.

2005-01-01

In Phebus (French in pile facility; PWR scale 1/5000) experiments, performed by the Institut de Radioprotection et de Surete Nucleaire, few quantities of organic iodides were registered after interaction between iodine and reactor containment paint. This study concerns all mechanisms of chemical reactions between iodine and the polymer of the paint in order to estimate the organic iodides released from the paint. At first, all the paint components had been identified. Several models of chemical sites of the polymer were synthesized and tested with iodine in different conditions of temperature and radiation. These experiments showed interactions between iodine and secondary or tertiary amines by charge transfer. In few cases, the complex of tertiary amines creates oxidation reactions. (author)

Multi-sectoral action for child safety-a European study exploring implicated sectors.

Science.gov (United States)

Scholtes, Beatrice; Schröder-Bäck, Peter; Förster, Katharina; MacKay, Morag; Vincenten, Joanne; Brand, Helmut

2017-06-01

Injury to children in Europe, resulting in both death and disability, constitutes a significant burden on individuals, families and society. Inequalities between high and low-income countries are growing. The World Health Organisation Health 2020 strategy calls for inter-sectoral collaboration to address injury in Europe and advocates the whole of government and whole of society approaches to wicked problems. In this study we explore which sectors (e.g. health, transport, education) are relevant for four domains of child safety (intentional injury, water, road and home safety). We used the organigraph methodology, originally developed to demonstrate how organizations work, to describe the governance of child safety interventions. Members of the European Child Safety Alliance, working in the field of child safety in 24 European countries, drew organigraphs of evidence-based interventions. They included the different actors involved and the processes between them. We analyzed the organigraphs by counting the actors presented and categorizing them into sectors using a pre-defined analysis framework. We received 44 organigraphs from participants in 24 countries. Twenty-seven sectors were identified across the four domains. Nine of the 27 identified sectors were classified as 'core sectors' (education, health, home affairs, justice, media, recreation, research, social/welfare services and consumers). This study reveals the multi-sectoral nature of child safety in practice. It provides information for stakeholders working in child safety to help them implement inter-sectoral child safety interventions taking a whole-of-government and whole-of-society approach to health governance. © The Author 2017. Published by Oxford University Press on behalf of the European Public Health Association. All rights reserved.

A Study on Enhancement of Understanding of Radiation and Safety Management

Energy Technology Data Exchange (ETDEWEB)

Yoo, Dong Han; Park, Ji Young; Lee, Jae Uk; Bae, Jun Woo; Kim, Hee Reyoung [Ulsan National Institute of Science and Technology, Ulsan (Korea, Republic of)

2014-10-15

Concerns for radiation exposure have been increased from small and big radiation works or experiments with radiation generator (RG) or radiation isotopes (RI) at institutions using radiation in Korea. Actually, due to radiation exposure occurred on the process of handling RI, etc., The exposure should be maintained as low as reasonably possible. To do this, above all, suitable training and establishment of safety culture have to be preceded. In this respect, an education institution is a place where people learn first about handling radiations in various specialties with purposes including academic research, and the first learned habits and practices acts as the basis for safety management of radiation when they continue to do radiation work after going into the society. Hereford, it is needed to establish the right safety culture on radiation for its safe managing. In the present study, the direction for the right understandings and safety improvement are suggested through the radiation survey on education institutions and preparation of safety guidances for users. The basic guidance at the radiation experiment was prepared for the right understanding of the radiation to prevent radiation accidents from careless handling by workers based on the surveyed results for education institutions. It is expected to be used as fundamentals for improvement for radiation safety management of workers and researchers and, further, safety policy for national nuclear energy and radiations.

A Study on Enhancement of Understanding of Radiation and Safety Management

International Nuclear Information System (INIS)

Yoo, Dong Han; Park, Ji Young; Lee, Jae Uk; Bae, Jun Woo; Kim, Hee Reyoung

2014-01-01

Concerns for radiation exposure have been increased from small and big radiation works or experiments with radiation generator (RG) or radiation isotopes (RI) at institutions using radiation in Korea. Actually, due to radiation exposure occurred on the process of handling RI, etc., The exposure should be maintained as low as reasonably possible. To do this, above all, suitable training and establishment of safety culture have to be preceded. In this respect, an education institution is a place where people learn first about handling radiations in various specialties with purposes including academic research, and the first learned habits and practices acts as the basis for safety management of radiation when they continue to do radiation work after going into the society. Hereford, it is needed to establish the right safety culture on radiation for its safe managing. In the present study, the direction for the right understandings and safety improvement are suggested through the radiation survey on education institutions and preparation of safety guidances for users. The basic guidance at the radiation experiment was prepared for the right understanding of the radiation to prevent radiation accidents from careless handling by workers based on the surveyed results for education institutions. It is expected to be used as fundamentals for improvement for radiation safety management of workers and researchers and, further, safety policy for national nuclear energy and radiations

Predicting safety culture: the roles of employer, operations manager and safety professional.

Science.gov (United States)

Wu, Tsung-Chih; Lin, Chia-Hung; Shiau, Sen-Yu

2010-10-01

This study explores predictive factors in safety culture. In 2008, a sample 939 employees was drawn from 22 departments of a telecoms firm in five regions in central Taiwan. The sample completed a questionnaire containing four scales: the employer safety leadership scale, the operations manager safety leadership scale, the safety professional safety leadership scale, and the safety culture scale. The sample was then randomly split into two subsamples. One subsample was used for measures development, one for the empirical study. A stepwise regression analysis found four factors with a significant impact on safety culture (R²=0.337): safety informing by operations managers; safety caring by employers; and safety coordination and safety regulation by safety professionals. Safety informing by operations managers (ß=0.213) was by far the most significant predictive factor. The findings of this study provide a framework for promoting a positive safety culture at the group level. Crown Copyright © 2010. Published by Elsevier Ltd. All rights reserved.

Maintaining and Researching Port Safety: A Case Study of the Port of Kaohsiung

OpenAIRE

Tseng, Po-Hsing.; Pilcher, Nick.

2017-01-01

Maintaining port safety in full conformity with IMO standards is a requisite for every port and country. To do this, understanding the challenges and human factors involved is key. To date, much research has shed valuable light on these factors and considered how to address them. One aspect that is often noted is that both maintaining port safety and researching port safety presents numerous challenges. This paper considers both these aspects in the context of a case study of port safety in K...

Plant air systems safety study: Portsmouth Gaseous Diffusion Plant

International Nuclear Information System (INIS)

1982-05-01

The Portsmouth Gaseous Diffusion Plant Air System facilities and operations are reviewed for potential safety problems not covered by standard industrial safety procedures. Information is presented under the following section headings: facility and process description (general); air plant equipment; air distribution system; safety systems; accident analysis; plant air system safety overview; and conclusion

The impact of health and safety committees. A study based on survey, interview, and Occupational Safety and Health Administration data.

Science.gov (United States)

Boden, L I; Hall, J A; Levenstein, C; Punnett, L

1984-11-01

In a study conducted to determine if the existence of a joint labor-management health and safety committee (HSC) was correlated with either the number of Occupational Safety and Health Administration (OSHA) complaints or hazardousness, as measured by OSHA serious citations, virtually no effect could be detected in a sample of 127 Massachusetts manufacturing firms. At a sample of 13 firms, interviews of HSC members were conducted. Committee attributes and perceptions about committee effectiveness were compared with the number of OSHA complaints and serious citations. There were fewer complaints and fewer serious citations at firms with HSCs that were perceived as effective. Results of the study suggest that the objective attributes of the committee may be less important to its success than the commitment of management and labor to solving workplace safety problems.

Labor unions and safety climate: perceived union safety values and retail employee safety outcomes.

Science.gov (United States)

Sinclair, Robert R; Martin, James E; Sears, Lindsay E

2010-09-01

Although trade unions have long been recognized as a critical advocate for employee safety and health, safety climate research has not paid much attention to the role unions play in workplace safety. We proposed a multiple constituency model of workplace safety which focused on three central safety stakeholders: top management, ones' immediate supervisor, and the labor union. Safety climate research focuses on management and supervisors as key stakeholders, but has not considered whether employee perceptions about the priority their union places on safety contributes contribute to safety outcomes. We addressed this gap in the literature by investigating unionized retail employee (N=535) perceptions about the extent to which their top management, immediate supervisors, and union valued safety. Confirmatory factor analyses demonstrated that perceived union safety values could be distinguished from measures of safety training, workplace hazards, top management safety values, and supervisor values. Structural equation analyses indicated that union safety values influenced safety outcomes through its association with higher safety motivation, showing a similar effect as that of supervisor safety values. These findings highlight the need for further attention to union-focused measures related to workplace safety as well as further study of retail employees in general. We discuss the practical implications of our findings and identify several directions for future safety research. 2009 Elsevier Ltd. All rights reserved.

Assessment of radiation safety awareness among nuclear medicine nurses: a pilot study

International Nuclear Information System (INIS)

Yunus, N A; Abdullah, M H R O; Said, M A; Ch'ng, P E

2014-01-01

All nuclear medicine nurses need to have some knowledge and awareness on radiation safety. At present, there is no study to address this issue in Malaysia. The aims of this study were (1) to determine the level of knowledge and awareness on radiation safety among nuclear medicine nurses at Putrajaya Hospital in Malaysia and (2) to assess the effectiveness of a training program provided by the hospital to increase the knowledge and awareness of the nuclear medicine nurses. A total of 27 respondents attending a training program on radiation safety were asked to complete a questionnaire. The questionnaire consists 16 items and were categorized into two main areas, namely general radiation knowledge and radiation safety. Survey data were collected before and after the training and were analyzed using descriptive statistics and paired sample t-test. Respondents were scored out of a total of 16 marks with 8 marks for each area. The findings showed that the range of total scores obtained by the nuclear medicine nurses before and after the training were 6-14 (with a mean score of 11.19) and 13-16 marks (with a mean score of 14.85), respectively. Findings also revealed that the mean score for the area of general radiation knowledge (7.59) was higher than that of the radiation safety (7.26). Currently, the knowledge and awareness on radiation safety among the nuclear medicine nurses are at the moderate level. It is recommended that a national study be conducted to assess and increase the level of knowledge and awareness among all nuclear medicine nurses in Malaysia

Assessment of radiation safety awareness among nuclear medicine nurses: a pilot study

Science.gov (United States)

Yunus, N. A.; Abdullah, M. H. R. O.; Said, M. A.; Ch'ng, P. E.

2014-11-01

All nuclear medicine nurses need to have some knowledge and awareness on radiation safety. At present, there is no study to address this issue in Malaysia. The aims of this study were (1) to determine the level of knowledge and awareness on radiation safety among nuclear medicine nurses at Putrajaya Hospital in Malaysia and (2) to assess the effectiveness of a training program provided by the hospital to increase the knowledge and awareness of the nuclear medicine nurses. A total of 27 respondents attending a training program on radiation safety were asked to complete a questionnaire. The questionnaire consists 16 items and were categorized into two main areas, namely general radiation knowledge and radiation safety. Survey data were collected before and after the training and were analyzed using descriptive statistics and paired sample t-test. Respondents were scored out of a total of 16 marks with 8 marks for each area. The findings showed that the range of total scores obtained by the nuclear medicine nurses before and after the training were 6-14 (with a mean score of 11.19) and 13-16 marks (with a mean score of 14.85), respectively. Findings also revealed that the mean score for the area of general radiation knowledge (7.59) was higher than that of the radiation safety (7.26). Currently, the knowledge and awareness on radiation safety among the nuclear medicine nurses are at the moderate level. It is recommended that a national study be conducted to assess and increase the level of knowledge and awareness among all nuclear medicine nurses in Malaysia.

Road safety effects of porous asphalt: a systematic review of evaluation studies

DEFF Research Database (Denmark)

Elvik, R.; Greibe, Poul

2005-01-01

of eighteen estimates of the effect of porous asphalt on accident rates. No clear effect on road safety of porous asphalt was found. All summary estimates of effect indicated very small changes in accident rates and very few were statistically significant at conventional levels. Studies that have evaluated...... of these changes in risk factors on accident occurrence cannot be predicted. On the whole, the research that has been reported so far regarding road safety effects of porous asphalt is inconclusive. The studies are not of high quality and the findings are inconsistent.......This paper presents a systematic review of studies that have evaluated the effects on road safety of porous asphalt. Porous asphalt is widely used on motorways in Europe, mainly in order to reduce traffic noise and increase road capacity. A meta-analysis was made of six studies, containing a total...

Safety Management. An Introduction to a Frame of Reference Exemplified with Case Studies from Non-Nuclear Contexts

Energy Technology Data Exchange (ETDEWEB)

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

2004-11-15

A systems perspective on safety management is introduced followed by two briefly presented case studies of safety management in non-nuclear contexts. The first study concerns a car manufacturer and the second study a road traffic tunnel system. The risks of a car accident in the first case study are evident. The great exposure generates many incidents and accidents. In the second study, the rather low traffic intensity through the tunnel produces few incidents and accidents and only a few fatal accidents over the years. Yet, the risk of the individual traveler is much greater in the tunnel than on the average road. The case studies are presented in a systems perspective with emphasis on information feedback about the risks of the systems. The first case study illustrates high quality safety management, while the second case study shows many weaknesses of the safety management in the tunnel system. Some differences in safety management between the case studies are noted. The last part of the study presents an organizational perspective on safety management and offers alternative theoretical perspectives on the concept of safety management. The report shows that further studies are needed both (1) to develop a frame of reference for describing safety management across industries and activities and (2) to collect data illustrating of good and poor safety management. Then, the results can be used to strengthen and/or improving safety management in the nuclear power industry and its regulators

Safety Management. An Introduction to a Frame of Reference Exemplified with Case Studies from Non-Nuclear Contexts

International Nuclear Information System (INIS)

Svensson, Ola; Salo, Ilkka

2004-11-01

A systems perspective on safety management is introduced followed by two briefly presented case studies of safety management in non-nuclear contexts. The first study concerns a car manufacturer and the second study a road traffic tunnel system. The risks of a car accident in the first case study are evident. The great exposure generates many incidents and accidents. In the second study, the rather low traffic intensity through the tunnel produces few incidents and accidents and only a few fatal accidents over the years. Yet, the risk of the individual traveler is much greater in the tunnel than on the average road. The case studies are presented in a systems perspective with emphasis on information feedback about the risks of the systems. The first case study illustrates high quality safety management, while the second case study shows many weaknesses of the safety management in the tunnel system. Some differences in safety management between the case studies are noted. The last part of the study presents an organizational perspective on safety management and offers alternative theoretical perspectives on the concept of safety management. The report shows that further studies are needed both (1) to develop a frame of reference for describing safety management across industries and activities and (2) to collect data illustrating of good and poor safety management. Then, the results can be used to strengthen and/or improving safety management in the nuclear power industry and its regulators

A Study on the Main Steam Safety Valve Opening Mechanism by Flashing on NPPs

International Nuclear Information System (INIS)

Kim, Bae Joo

2009-01-01

A safety injection event happened by opening of the Main Steam Safety Valve at Kori unit 1 on April 16, 2005. The safety valves were opened at the lower system pressure than the valve opening set point due to rapid system pressure drop by opening of the Power Operated Relief Valve installed at the upstream of the Main Steam System. But the opening mechanism of safety valve at the lower set point pressure was not explained exactly. So, it needs to be understood about the safety valve opening mechanism to prevent a recurrence of this kind of event at a similar system of Nuclear Power Plant. This study is aimed to suggest the hydrodynamic mechanism for the safety valve opening at the lower set point pressure and the possibility of the recurrence at similar system conditions through document reviewing for the related previous studies and Kori unit 1 event

Collaboration and patient safety at an emergency department - a qualitative case study.

Science.gov (United States)

Pedersen, Anna Helene Meldgaard; Rasmussen, Kurt; Grytnes, Regine; Nielsen, Kent Jacob

2018-03-19

Purpose The purpose of this paper is to examine how conflicts about collaboration between staff at different departments arose during the establishment of a new emergency department and how these conflicts affected the daily work and ultimately patient safety at the emergency department. Design/methodology/approach This qualitative single case study draws on qualitative semi-structured interviews and participant observation. The theoretical concepts "availability" and "receptiveness" as antecedents for collaboration will be applied in the analysis. Findings Close collaboration between departments was an essential precondition for the functioning of the new emergency department. The study shows how a lack of antecedents for collaboration affected the working relation and communication between employees and departments, which spurred negative feelings and reproduced conflicts. This situation was seen as a potential threat for the safety of the emergency patients. Research limitations/implications This study presents a single case study, at a specific point in time, and should be used as an illustrative example of how contextual and situational factors affect the working environment and through that patient safety. Originality/value Few studies provide an in-depth investigation of what actually takes place when collaboration between professional groups goes wrong and escalates, and how problems in collaboration may affect patient safety.

Nurses' experiences and perspectives on medication safety practices: an explorative qualitative study.

Science.gov (United States)

Smeulers, Marian; Onderwater, Astrid T; van Zwieten, Myra C B; Vermeulen, Hester

2014-04-01

To explore nurses' experiences with and perspectives on preventing medication administration errors. Insight into nurses' experiences with and perspectives on preventing medication administration errors is important and can be utilised to tailor and implement safety practices. A qualitative interview study of 20 nurses in an academic medical centre was conducted between March and December of 2011. Three themes emerged from this study: (1) nurses' roles and responsibilities in medication safety: aside from safe preparation and administration, the clinical reasoning of nurses is essential for medication safety; (2) nurses' ability to work safely: knowledge of risks and nurses' work circumstances influence their ability to work safely; and (3) nurses' acceptance of safety practices: advantages, feasibility and appropriateness are important incentives for acceptance of a safety practice. Nurses' experiences coincide with the assumption that they are in a pre-eminent position to enable safe medication management; however, their ability to adequately perform this role depends on sufficient knowledge to assess the risks of medication administration and on the circumstances in which they work. Safe medication management requires a learning climate and professional practice environment that enables further development of professional nursing skills and knowledge. © 2014 John Wiley & Sons Ltd.

Work Practice, Safety and Heedfulness. Studies of Organizational Reliability in Hospitals and Nuclear Power Plants

International Nuclear Information System (INIS)

Gauthereau, Vincent

2003-01-01

The study of safety in complex systems has focused on different issues over the past decades. This focus was often linked to the conclusions of previous accidents'/incidents' analyses. When accidents were attributed to technical causes, safety research focused on technical developments. When they were later attributed to 'human errors', safety research focused on this 'component'. And when, since the mid-eighties accidents have been attributed to 'organizational factors', safety research has focused on these very same 'organizational factors'. The present thesis argues for a 'practice view' over safety to be taken. This view is mainly drawn from the field of research on High Reliability Organizations (HRO). HRO theorists' point of view on safety is that we can operate complex systems safely despite the fact that we have made them so complex that they are prone to 'normal accidents'. Humans involved in the operation of our systems actually create safety. Safety is formed through the adaptation of work practice to local conditions, and this adaptation is part of safe operation. Safety is not only a substantial quality of our socio-technical systems: the discursive dimension of safety actually seems to be a central component of safety creation. However, the adaptive ability of HRO can sometimes become their downfall. Adaptation, which is the backbone of safety, can sometimes be a drawback as well. Consequently, the practice view of safety, proposed in the present work, argues that we need to further comprehend how work practice evolves over time, and more specifically what are the inherent characteristics of work practice that create this evolution. Empirical studies from health-care and nuclear power generation highlight different details about organizational reliability. For instance, one study of planning at a nuclear power plant draws our attention to the different roles of planning in the organization. Another study, within heath-care, underlines the evolution of

Patients for patient safety in China: a cross sectional study.

Science.gov (United States)

Zhang, Qiongwen; Li, Yulin; Li, Jing; Mao, Xuanyue; Zhang, Lijuan; Ying, Qinghua; Wei, Xin; Shang, Lili; Zhang, Mingming

2012-02-01

To investigate the baseline status of patients' awareness, knowledge, and attitudes to patient safety in China, and to determine the factors that influence patients' involvement in patient safety. We conducted a cross sectional survey using questionnaires adapted from recent studies on patient safety from outside China. The items included medical errors, infection, medication safety, and other aspects of patient safety. The questionnaire included 17 items and 5 domains. The survey was conducted between Jan. 2009 and Dec. 2010 involving 1000 patients from ten grade-A hospitals in seven provinces or cities in China. Most patients from the surgery departments completed the questionnaires voluntarily and anonymously. Five reviewers independently input the data into Microsoft Excel 2003, and the data were double-checked. Data were analyzed using SPSS 15.0 software for differences in the perceptions and attitudes of patients toward patient safety among different genders, ages, and regions. We distributed 1000 questionnaires and collected 959 completed questionnaires (response rate: 96%). Among the respondents, 58% of patients did not know what medical error is. Sixty-five percent of patients wanted disclosure of all medical errors. After errors occurred, 58% of patients wanted explanations of all possible harms that had resulted. Among 187 patients who had experienced medical errors, 83% of patients had sought appropriate legal action. About 52% of patients understood hospital infection, but 28% patients did not know that infections could occur in hospital. Seventy-eight percent of patients thought that medical staff should wash their hands before examining patients. More than half of the patients (68%) were willing to remind the staff of hygiene if they saw unsanitary conditions in a health clinic. Only 14% of patients knew the side effects of medications that they took. The majority of patients surveyed expressed willingness to contribute to patient safety, but their

Hospital safety climate and safety behavior: A social exchange perspective.

Science.gov (United States)

Ancarani, Alessandro; Di Mauro, Carmela; Giammanco, Maria D

Safety climate is considered beneficial to the improvement of hospital safety outcomes. Nevertheless, the relations between two of its key constituents, namely those stemming from leader-subordinate relations and coworker support for safety, are still to be fully ascertained. This article uses the theoretical lens of Social Exchange Theory to study the joint impact of leader-member exchange in the safety sphere and coworker support for safety on safety-related behavior at the hospital ward level. Social exchange constructs are further related to the existence of a shame-/blame-free environment, seen as a potential antecedent of safety behavior. A cross-sectional study including 166 inpatients in hospital wards belonging to 10 public hospitals in Italy was undertaken to test the hypotheses developed. Hypothesized relations have been analyzed through a fully mediated multilevel structural equation model. This methodology allows studying behavior at the individual level, while keeping into account the heterogeneity among hospital specialties. Results suggest that the linkage between leader support for safety and individual safety behavior is mediated by coworker support on safety issues and by the creation of a shame-free environment. These findings call for the creation of a safety climate in which managerial efforts should be directed not only to the provision of new safety resources and the enforcement of safety rules but also to the encouragement of teamwork and freedom to report errors as ways to foster the capacity of the staff to communicate, share, and learn from each other.

Authorization Decree Application for the creation of the Flamanville-3 Basic Nuclear Installation. Executive Summary of the Technical Review

International Nuclear Information System (INIS)

2009-01-01

On 9 May 2006, Electricite de France (EDF) submitted to the Ministers for Nuclear Safety an authorization decree application for an EPR-type reactor on the site of the Flamanville Nuclear Power Plant (NPP). Article 29 of Act No. 2006-686 of 13 June 2006 on Transparency and Security in the Nuclear Field prescribes that the creation of any basic nuclear installation shall be issued by a decree taken after consultation with the Nuclear Safety Authority (Autorite de surete nucleaire - ASN). The purpose of this report is to provide ASN's Board with a summary of the technical review led by ASN services and carried out by their technical support agencies, namely the IRSN, the GPR and the Standing Nuclear Section of the CCAP between 2001 and 2006. After summing up the conclusions of the review on the safety options of the European Pressurized Reactor (EPR) Project, as carried out between 1993 and 2000, this report describes the process and modalities of the review conducted from 2001 to 2006. Besides providing the opinion of ASN's services on the creation-licence application, it also outlines the further review to be carried out, if the authorization decree is issued. (authors)

A study of the international trend and comprehensive enhancement program on the Nuclear Power Plant safety

International Nuclear Information System (INIS)

Jang, Soon Hong; Cho, Nam Jin; Paek, Won Phil

1990-12-01

The objectives of this study are as follows : overview of the international trend related to the safety of Nuclear Power Plant(NPPs), study of the present status of NPP safety in Korea in aspects of design, construction and operation, suggestion of the comprehensive program to improve NPP safety in Korea. The results of this study can contribute to improve the safety of existing and future NPPs, and to establish the severe accident policy in Korea

A study of the international trend and comprehensive enhancement program on the Nuclear Power Plant safety

Energy Technology Data Exchange (ETDEWEB)

Jang, Soon Hong; Cho, Nam Jin; Paek, Won Phil [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

1990-12-15

The objectives of this study are as follows : overview of the international trend related to the safety of Nuclear Power Plant(NPPs), study of the present status of NPP safety in Korea in aspects of design, construction and operation, suggestion of the comprehensive program to improve NPP safety in Korea. The results of this study can contribute to improve the safety of existing and future NPPs, and to establish the severe accident policy in Korea.

Safety evaluations required in the safety regulations for Monju and the validity confirmation of safety evaluation methods

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

The purposes of this study are to perform the safety evaluations of the fast breeder reactor 'Monju' and to confirm the validity of the safety evaluation methods. In JFY 2012, the following results were obtained. As for the development of safety evaluation methods needed in the safety examination achieved for the reactor establishment permission, development of the analysis codes, such as a core damage analysis code, were carried out according to the plan. As for the development of the safety evaluation method needed for the risk informed safety regulation, the quantification technique of the event tree using the Continuous Markov chain Monte Carlo method (CMMC method) were studied. (author)

Identifying research priorities for patient safety in mental health: an international expert Delphi study

Science.gov (United States)

Murray, Kevin; Thibaut, Bethan; Ramtale, Sonny Christian; Adam, Sheila; Darzi, Ara; Archer, Stephanie

2018-01-01

Objective Physical healthcare has dominated the patient safety field; research in mental healthcare is not as extensive but findings from physical healthcare cannot be applied to mental healthcare because it delivers specialised care that faces unique challenges. Therefore, a clearer focus and recognition of patient safety in mental health as a distinct research area is still needed. The study aim is to identify future research priorities in the field of patient safety in mental health. Design Semistructured interviews were conducted with the experts to ascertain their views on research priorities in patient safety in mental health. A three-round online Delphi study was used to ascertain consensus on 117 research priority statements. Setting and participants Academic and service user experts from the USA, UK, Switzerland, Netherlands, Ireland, Denmark, Finland, Germany, Sweden, Australia, New Zealand and Singapore were included. Main outcome measures Agreement in research priorities on a five-point scale. Results Seventy-nine statements achieved consensus (>70%). Three out of the top six research priorities were patient driven; experts agreed that understanding the patient perspective on safety planning, on self-harm and on medication was important. Conclusions This is the first international Delphi study to identify research priorities in safety in the mental field as determined by expert academic and service user perspectives. A reasonable consensus was obtained from international perspectives on future research priorities in patient safety in mental health; however, the patient perspective on their mental healthcare is a priority. The research agenda for patient safety in mental health identified here should be informed by patient safety science more broadly and used to further establish this area as a priority in its own right. The safety of mental health patients must have parity with that of physical health patients to achieve this. PMID:29502096

Reactor safety

International Nuclear Information System (INIS)

Butz, H.P.; Heuser, F.W.; May, H.

1985-01-01

The paper comprises an introduction into nuclear physics bases, the safety concept generally speaking, safety devices of pwr type reactors, accident analysis, external influences, probabilistic safety assessment and risk studies. It further describes operational experience, licensing procedures under the Atomic Energy Law, research in reactor safety and the nuclear fuel cycle. (DG) [de

A Study on University Student's Perception of Food Safety

International Nuclear Information System (INIS)

Koh, K.H.

2007-01-01

The present study compared the perception of food safety between students majoring in Food Science and Nutrition and other students who are ordinary food consumers. The importance of factors related to food safety was high in order of pesticide residue (45%), food additives (24%), food pathogens (15%), GM foods (7%), antibiotics (4%) and irradiated foods (4%), and no significant difference was observed according to major(p less than 0.10). Particularly with regard to irradiated food, students majoring in Food Science and Nutrition replied 'no hamful' (21%), 'harmful' (58%) or 'not sure' (21%), showing that more than half of them thought that irradiated food is harmful

Safety assessment in plant layout design using indexing approach: implementing inherent safety perspective. Part 2-Domino Hazard Index and case study.

Science.gov (United States)

Tugnoli, Alessandro; Khan, Faisal; Amyotte, Paul; Cozzani, Valerio

2008-12-15

The design of layout plans requires adequate assessment tools for the quantification of safety performance. The general focus of the present work is to introduce an inherent safety perspective at different points of the layout design process. In particular, index approaches for safety assessment and decision-making in the early stages of layout design are developed and discussed in this two-part contribution. Part 1 (accompanying paper) of the current work presents an integrated index approach for safety assessment of early plant layout. In the present paper (Part 2), an index for evaluation of the hazard related to the potential of domino effects is developed. The index considers the actual consequences of possible escalation scenarios and scores or ranks the subsequent accident propagation potential. The effects of inherent and passive protection measures are also assessed. The result is a rapid quantification of domino hazard potential that can provide substantial support for choices in the early stages of layout design. Additionally, a case study concerning selection among various layout options is presented and analyzed. The case study demonstrates the use and applicability of the indices developed in both parts of the current work and highlights the value of introducing inherent safety features early in layout design.

Light-water reactors. Safety problems and related studies in France

International Nuclear Information System (INIS)

Lelievre, J.

1975-01-01

The program of theoretical and experimental studies developed by the CEA on the safety of PWR reactors is presented: studies relative to the consequences of a LOCA following a rupture of the primary system, studies relative to fuel element behavior, studies on steels, reliability studies and studies of non-destructive testing methods [fr

Fusion safety studies in Russia from 1996 to 2000

Energy Technology Data Exchange (ETDEWEB)

Kolbasov, B.N. E-mail: kolbasov@nfi.kiae.ru; Biryukov, A.Yu.; Davydov, D.A.; Guseva, M.I.; Khripunov, B.I.; Korshunov, S.N.; Martynenko, Yu.V.; Romanov, P.V.; Vasiliev, V.I

2001-04-01

The paper is a review of results of some fusion safety studies performed in Russia during 1996-2000 (after the 6th IAEA Technical Committee Meeting on 'Developments in Fusion Safety'). In particular, changes of hydrogen isotope inventory in co-deposited layers on tungsten and graphite under simulation of normal tokamak operation and plasma disruptions are reported. Size distribution of graphite and W-Be-dust under the experiments at issue revealed two maximums. Erosion products were collected within tokamak T-10. Their microstructure and chemical composition were studied and are reported in the paper. Chemical interaction of beryllium powder with steam (in temperature range of 400-600 deg. C) and air (at 500-1000 deg. C) was investigated. Mathematical models describing it were developed. Chemical interaction of Be-powder with carbon was studied too. A dependence of beryllium carbide layer thickness growth versus time at 950 deg. C was found on the basis of the experiments.

Impact of individual resilience and safety climate on safety performance and psychological stress of construction workers: A case study of the Ontario construction industry.

Science.gov (United States)

Chen, Yuting; McCabe, Brenda; Hyatt, Douglas

2017-06-01

The construction industry has hit a plateau in terms of safety performance. Safety climate is regarded as a leading indicator of safety performance; however, relatively little safety climate research has been done in the Canadian construction industry. Safety climate may be geographically sensitive, thus it is necessary to examine how the construct of safety climate is defined and used to improve safety performance in different regions. On the other hand, more and more attention has been paid to job related stress in the construction industry. Previous research proposed that individual resilience may be associated with a better safety performance and may help employees manage stress. Unfortunately, few empirical research studies have examined this hypothesis. This paper aims to examine the role of safety climate and individual resilience in safety performance and job stress in the Canadian construction industry. The research was based on 837 surveys collected in Ontario between June 2015 and June 2016. Structural equation modeling (SEM) techniques were used to explore the impact of individual resilience and safety climate on physical safety outcomes and on psychological stress among construction workers. The results show that safety climate not only affected construction workers' safety performance but also indirectly affected their psychological stress. In addition, it was found that individual resilience had a direct negative impact on psychological stress but had no impact on physical safety outcomes. These findings highlight the roles of both organizational and individual factors in individual safety performance and in psychological well-being. Construction organizations need to not only monitor employees' safety performance, but also to assess their employees' psychological well-being. Promoting a positive safety climate together with developing training programs focusing on improving employees' psychological health - especially post-trauma psychological

Ageing study of the engineered safety features actuation system of the Loviisa NPP

International Nuclear Information System (INIS)

Simola, K.; Maskuniitty, M.

1995-06-01

An ageing study of the engineered safety features actuation system of the Loviisa nuclear power plant has been performed. The operating experience, including failure and maintenance histories of analog measuring devices, logics for safety signal formation and individual control electronics of pumps and valves, has been collected and analysed. The safety importance of system components has been studied with a fault tree analysis of a selected safety function. Based on the results of the analysis of operating experiences and the fault tree analysis, some components were selected for deeper analyses. According to the operating experience, the amount of failures in the Loviisa plant safety system has been low and no increasing trend in the failure history can yet be observed. Only a few failures had prohibited the propagation of the safety signal, mostly the failures have caused a false alarm. The failures reported have concerned mainly limit signal units, transmitters, and priority units. According to the fault tree analysis of one safety function, the most important components of this subsystem are individual control units and pulse/DC converters. Failure modes and effect analyses were performed for priority and individual control unit, limit signal unit and comparator and pulse/DC converter in order to identify the critical failure modes of these devices. (orig.) (15 refs., 26 figs., 9 tabs.)

Cannabis for the Management of Pain: Assessment of Safety Study (COMPASS).

Science.gov (United States)

Ware, Mark A; Wang, Tongtong; Shapiro, Stan; Collet, Jean-Paul

2015-12-01

Cannabis is widely used as a self-management strategy by patients with a wide range of symptoms and diseases including chronic non-cancer pain. The safety of cannabis use for medical purposes has not been systematically evaluated. We conducted a prospective cohort study to describe safety issues among individuals with chronic non-cancer pain. A standardized herbal cannabis product (12.5% tetrahydrocannabinol) was dispensed to eligible individuals for a 1-year period; controls were individuals with chronic pain from the same clinics who were not cannabis users. The primary outcome consisted of serious adverse events and non-serious adverse events. Secondary safety outcomes included pulmonary and neurocognitive function and standard hematology, biochemistry, renal, liver, and endocrine function. Secondary efficacy parameters included pain and other symptoms, mood, and quality of life. Two hundred and fifteen individuals with chronic pain were recruited to the cannabis group (141 current users and 58 ex-users) and 216 controls (chronic pain but no current cannabis use) from 7 clinics across Canada. The median daily cannabis dose was 2.5 g/d. There was no difference in risk of serious adverse events (adjusted incidence rate ratio = 1.08, 95% confidence interval = .57-2.04) between groups. Medical cannabis users were at increased risk of non-serious adverse events (adjusted incidence rate ratio = 1.73, 95% confidence interval = 1.41-2.13); most were mild to moderate. There were no differences in secondary safety assessments. Quality-controlled herbal cannabis, when used by patients with experience of cannabis use as part of a monitored treatment program over 1 year, appears to have a reasonable safety profile. Longer-term monitoring for functional outcomes is needed. The study was registered with www.controlled-trials.com (ISRCTN19449752). This study evaluated the safety of cannabis use by patients with chronic pain over 1 year. The study found that there was a higher

Safety probabilistic study of Almirante Alvaro Alberto nuclear power plant-Unit I

International Nuclear Information System (INIS)

Lederman, L.; Arrieta, L.A.I.; Fernandes Filho, T.L.; Gibelli, S.M.O.; Berthoud, J.S.; Ambros, P.C.; Soares, H.V.; Camargo, C.T.M.

1985-04-01

The phase A of probabilistic safety study of Angra I nuclear power plant is presented, to be used by CNEN and FURNAS Centrais Eletricas S.A. as standard model in operational and safety analysis. The methodology applied is a modernization of WASH 1400/2.11/ study. Angra I safety systems are described. The selection and qualification of initiating sequence accident events which can damage the reactor core are done. The accident scenes are developed using the method of event trees. The reactor in subcritical condition (pressure, fuel temperature within limits and controlled level of reactor vessel) is studied during 24 hours. The uncertainness in failure probabilities of systems and in the determination of sequence frequencies for core danification are evaluated. Total frequency of sequences which cause the fusion of reactor core are presented. (M.C.K.) [pt

Surveillance of health care workers exposed to ionising radiation: Rimed pilot study

International Nuclear Information System (INIS)

2008-01-01

The project so-called RIMED aimed to set up epidemiological surveillance of health care workers exposed to ionizing radiation. A pilot study was conducted in a sample of hospital personnel to examine the possibility of identifying exposed subjects in order to analyse mortality patterns according to occupational characteristics such as medical departments or occupations in a historical cohort. Seven hospitals participated in this pilot study. Health-care workers who had worn a dosimeter up to December 2003 were to be included in this cohort. The subjects' identification data were obtained from the SISERI (Systeme d'information de la surveillance de l'exposition aux rayonnements ionisants - Ionizing Radiation Exposure Monitoring Information System) database managed by the Institut de radioprotection et de surete nucleaire - Radiation Protection and Nuclear Safety Institute (IRSN). The SISERI system was in a 'pilot' phase in 2004. According to SISERI database, a total of 5126 subjects were found to have worn a dosimeter up to December 2003. The subjects' identification data were completed by the administrative services of the hospitals and occupational physicians searched for subjects' occupational data. Information required for the vital status search was satisfactorily completed only for 38% of the cohort subjects. This pilot study showed that obtaining data from SISERI database completed by hospital administrative data in 2004 led to a database of insufficient quality for epidemiological surveillance. The Institut de veille sanitaire (French Institute of Public Health Surveillance) recommends that transmission by the employers of some specific personal or occupational data of the exposed subjects should be made compulsory. In this way, SISERI system should be able to constitute any database with required quality for epidemiological surveillance of ionizing radiation exposed subjects. (authors)

Food safety issues in China: a case study of the dairy sector.

Science.gov (United States)

Dong, Xiaoxia; Li, Zhemin

2016-01-15

Over the past 10 years, food safety incidents have occurred frequently in China. Food safety issues in the dairy sector have increasingly gained the attention of the Chinese government and the public. The objective of this research is to explore consumption changes of dairy products of different income groups after these dairy safety incidents. The research indicates that consumers' response to dairy safety risk is very intense. Dairy consumption has experienced a declining trend in recent years, and the impact of dairy safety incidents has lasted for at least 5 years. Until 2012, dairy consumption had not yet fully recovered from this influence. Using the random effects model, this study examined the relationship between food safety incident and consumption. Overall, the results show that consumers in the low-income group are more sensitive to safety risk than those in the high-income group. It can be seen from this paper that the decrease of urban residents' dairy consumption was mainly driven by changes in fresh milk consumption, while the decline of milk powder consumption, which was affected by the melamine incident, was relatively moderate, and milk powder consumption for the high-income group even increased. © 2015 Society of Chemical Industry.

Pegase: safety studies - experimental study of burn-out risks in transient operation; Pegase: etude de surete - etude experimentale des risques de burn out en regime transitoire

Energy Technology Data Exchange (ETDEWEB)

Vernier, P [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

1968-07-01

An experiment out-of-pile experimental set up is proposed simulating the breakage of a pipe supplying the core of the reactor Pegase. The two fast phenomena, depressurization of the vessel and flow reversal, are reproduced. The aluminium heating channel has the same shape as that of the reactor channel but has twice the heat capacity. The starting conditions are V= 4.50 and 6 m/sec., T{sub E} = 50 and 60 degrees C and P{sub E} = 4 bars. The results show that the critical flux PHI{sub C} varies with the flow-rate from 45 to 60 W/cm{sup 2} in the case where there is no power reduction. For fluxes of 90 W/cm{sup 2} the results lead to the conclusion that the hot channel attains a state of burn-out after 0.1 sec. and that its temperature reaches 500 C in 0.8 sec. The hydrodynamic conditions in the channels after the accident involve periodic expulsion (0.2 to 0.5 sec.), characteristic of boiling at low pressure. A study of the steady state flow redistribution through a by-pass has given flux redistribution PHI{sub R} of 190 W/cm{sup 2} for a flow rate of 4.5 m/sec. at 50 and of 175 W/cm{sup 2} at 60 C. These values increase which has to be made between the critical flux PHI{sub C} during the periodic expulsion conditions and the flux redistribution PHI{sub R} during the steady state, has been shown. (author) [French] On propose un schema experimental hors pile d'une rupture du tuyau alimentant le coeur du reacteur PEGASE. On reproduit les phenomenes rapides de depressurisation du caisson et d'inversion du debit dans le coeur. Le canal chauffant en aluminium a la meme geometrie que le canal du reacteur, mais une capacite calorifique double. Les conditions initiales sont V= 4.5 et 6 m/s, T{sub E} = 50 et 60 C et P{sub E} = 4 bars. Les resultats montrent que le flux critique PHI{sub C} evolue avec la vitesse de 45 a 60 60 W/cm{sup 2} dans le cas ou il n'y a pas reduction de puissance. Pour des flux de 90 W/cm{sup 2} l'interpretation des resultats permet de conclure que le

Ageing degradation mechanisms in nuclear power plants: lessons learned from operating experience

International Nuclear Information System (INIS)

Bieth, M.; Zerger, B.; Duchac, A.

2014-01-01

This paper presents main results of a comprehensive study performed by the European Clearinghouse on Operating Experience Feedback of Nuclear Power Plants (NPP) with the support of IRSN (Institut de Surete Nucleaire et de Radioprotection) and GRS (Gesellschaft fuer Anlagen und Reaktorsicherheit mbH). Physical ageing mechanisms of Structures, Systems and Components (SSC) that eventually lead to ageing related systems and components failures at nuclear power plants were the main focus of this study. The analysis of ageing related events involved operating experience reported by NPP operators in France, Germany, USA and to the IAEA/NEA International Reporting System on operating experience for the past 20 years. A list of relevant ageing related events was populated. Each ageing related event contained in the list was analyzed and results of analysis were summarized for each ageing degradation mechanism which appeared to be the dominant contributor or direct cause. This paper provides insights into ageing related operating experience as well as recommendations to deal with the physical ageing of nuclear power plant SSC important to safety. (authors)

The control equipment of the Melusine II reactor; L'equipement de controle du reacteur Melusine II

Energy Technology Data Exchange (ETDEWEB)

Cordelle, M; Delcroix, V; Denis, P; Gariod, R

1963-07-01

Melusine II, low-power reactor, used for the study of Siloe core has diverged at the CEA Grenoble, the 23. May 1962; its monitoring board studied and carried out in this center is the first in France to be entirely transistorized. The first months of running have justified the hope put in the new electronics to improve the stability and the safety of running. The article describes the design of the control and gives the main characteristics of the measurement chains and of the actions on reactivity. (O.M.) [French] Melusine II, reacteur de faible puissance destine a l'etude du coeur de Siloe a diverge au Centre d'Etudes Nucleaires de Grenoble, le 23 mai 1962, son tableau de controle etudie et realise dans ce Centre est le premier en France a etre entierement transistorise. Les premiers mois de fonctionnement ont justifie l'espoir mis dans la nouvelle electronique pour ameliorer la stabilite et la surete de fonctionnement. L'article decrit la conception du controle et donne les principales caracteristiques des chaines de mesure et des actions sur la reactivite. (auteurs)

Study on occupational safety and health strategy for Taiwan.

Science.gov (United States)

Chuang, Kuen-Yuan; Su, Teh-Sheng; Kuo, Chao-Yin; Lin, Chien-Liang; Lin, Han-Yu; Yu, Yi-Chun

2009-12-01

The aim of this study was to establish a set of occupational safety and health (OSH) issues and development policies suitable for adoption in Taiwan. A survey was conducted on a sample of 102 experts and 235 industrial work safety personnel in Taiwan for statistical analysis of the general consensus, with the results showing such consensus in 104 individual policy indicators. Our results reveal that the most appropriate targets were considered to be annual 10% reductions in the 'occupational accident disability rate', 'occupational accident injury rate' and 'occupational diseases before 2010'. Responding to the specific question of the appropriate method of achieving a reduction in the number of accidents in Taiwan, the primary consideration for 13.4% of the experts and 10.6% of the industry personnel was 'promoting OSH awareness and enhancing the overall safety culture'. As regards the current OSH policy focus, 11.2% of the experts considered 'improving OSH legislation, standards and systems' to be the most important, whilst 8.9% of the industry personnel felt that 'recognizing work stress, overwork and emerging OSH issues' were the most important.

A Study on the Holding Capacity Safety Factors for Torpedo Anchors

Directory of Open Access Journals (Sweden)

Luís V. S. Sagrilo

2012-01-01

Full Text Available The use of powerful numerical tools based on the finite-element method has been improving the prediction of the holding capacity of fixed anchors employed by the offshore oil industry. One of the main achievements of these tools is the reduction of the uncertainty related to the holding capacity calculation of these anchors. Therefore, it is also possible to reduce the values of the associated design safety factors, which have been calibrated relying on models with higher uncertainty, without impairing the original level of structural safety. This paper presents a study on the calibration of reliability-based safety factors for the design of torpedo anchors considering the statistical model uncertainty evaluated using results from experimental tests and their correspondent finite-element-based numerical predictions. Both working stress design (WSD and load and resistance factors design (LRFD design methodologies are investigated. Considering the WSD design methodology, the single safety is considerably lower than the value typically employed in the design of torpedo anchors. Moreover, a LRFD design code format for torpedo anchors is more appropriate since it leads to designs having less-scattered safety levels around the target value.

Application of patient safety indicators internationally: a pilot study among seven countries.

Science.gov (United States)

Drösler, Saskia E; Klazinga, Niek S; Romano, Patrick S; Tancredi, Daniel J; Gogorcena Aoiz, Maria A; Hewitt, Moira C; Scobie, Sarah; Soop, Michael; Wen, Eugene; Quan, Hude; Ghali, William A; Mattke, Soeren; Kelley, Edward

2009-08-01

To explore the potential for international comparison of patient safety as part of the Health Care Quality Indicators project of the Organization for Economic Co-operation and Development (OECD) by evaluating patient safety indicators originally published by the US Agency for Healthcare Research and Quality (AHRQ). A retrospective cross-sectional study. Acute care hospitals in the USA, UK, Sweden, Spain, Germany, Canada and Australia in 2004 and 2005/2006. Routine hospitalization-related administrative data from seven countries were analyzed. Using algorithms adapted to the diagnosis and procedure coding systems in place in each country, authorities in each of the participating countries reported summaries of the distribution of hospital-level and overall (national) rates for each AHRQ Patient Safety Indicator to the OECD project secretariat. Each country's vector of national indicator rates and the vector of American patient safety indicators rates published by AHRQ (and re-estimated as part of this study) were highly correlated (0.821-0.966). However, there was substantial systematic variation in rates across countries. This pilot study reveals that AHRQ Patient Safety Indicators can be applied to international hospital data. However, the analyses suggest that certain indicators (e.g. 'birth trauma', 'complications of anesthesia') may be too unreliable for international comparisons. Data quality varies across countries; undercoding may be a systematic problem in some countries. Efforts at international harmonization of hospital discharge data sets as well as improved accuracy of documentation should facilitate future comparative analyses of routine databases.

The interplay between teamwork, clinicians' emotional exhaustion, and clinician-rated patient safety: a longitudinal study.

Science.gov (United States)

Welp, Annalena; Meier, Laurenz L; Manser, Tanja

2016-04-19

Effectively managing patient safety and clinicians' emotional exhaustion are important goals of healthcare organizations. Previous cross-sectional studies showed that teamwork is associated with both. However, causal relationships between all three constructs have not yet been investigated. Moreover, the role of different dimensions of teamwork in relation to emotional exhaustion and patient safety is unclear. The current study focused on the long-term development of teamwork, emotional exhaustion, and patient safety in interprofessional intensive care teams by exploring causal relationships between these constructs. A secondary objective was to disentangle the effects of interpersonal and cognitive-behavioral teamwork. We employed a longitudinal study design. Participants were 2100 nurses and physicians working in 55 intensive care units. They answered an online questionnaire on interpersonal and cognitive-behavioral aspects of teamwork, emotional exhaustion, and patient safety at three time points with a 3-month lag. Data were analyzed with cross-lagged structural equation modeling. We controlled for professional role. Analyses showed that emotional exhaustion had a lagged effect on interpersonal teamwork. Furthermore, interpersonal and cognitive-behavioral teamwork mutually influenced each other. Finally, cognitive-behavioral teamwork predicted clinician-rated patient safety. The current study shows that the interrelations between teamwork, clinician burnout, and clinician-rated patient safety unfold over time. Interpersonal and cognitive-behavioral teamwork play specific roles in a process leading from clinician emotional exhaustion to decreased clinician-rated patient safety. Emotionally exhausted clinicians are less able to engage in positive interpersonal teamwork, which might set in motion a vicious cycle: negative interpersonal team interactions negatively affect cognitive-behavioral teamwork and vice versa. Ultimately, ineffective cognitive

Study on real working performance and overload safety factor of high arch dam

Institute of Scientific and Technical Information of China (English)

2008-01-01

Considering the fact that high arch dams have problems such as complicated stress,high cost,and hazards after being damaged,this paper intends to study the effects of load,material strength,and safety analysis method on dam safety and working performance of arch dams.In this article,the effects of temperature,self weight exaction way and water loading on structure response are first discussed,and a more reasonable way of considering is then put forward.By taking into consideration the mechanical property of materials and comparing the effects of different yield criteria on overloading safety of high arch dams,this paper concludes that brittle characteristics of concrete should be fully considered when conducting safety assessment for high arch dams to avoid overestimating the bearing capacity of the dams.By comparing several typical projects,this paper works out a safety assessment system of multiple safety and relevant engineering analogical analysis methods,which is closer to the actual situation,and thus is able to assess the response of high arch dam structure in a more comprehensive way,elicit the safety coefficients in different situations,and provide a new way of considering the safety assessment of high arch dams.

The ISRN has assessed the safety and radioprotection of the solid radioactive waste management area at CEA/Saclay; L'IRSN a expertise la surete et la radioprotection de la zone de gestion des dechets radioactifs solides du CEA/Saclay

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-07-01

Completed by a report of a Permanent Group of Experts on the safety re-examination for the solid radioactive waste management area of the CEA/Saclay, this paper is a statement of the assessment by the IRSN (the French Institute of Radioprotection and Nuclear Safety) of this safety re-examination. It first recalls what a safety re-examination is for a nuclear installation and indicates the documents which have been transmitted by the CEA and analysed. Then, it briefly describes the activities which are performed in the concerned area: collecting, warehousing, conditioning, control and shipping of solid radioactive wastes or useless fuels. The IRSN comments the works done and to be done for the different operations on different types of waste (low or middle activity), and then the different aspects of the installation safety (radiations, confining, fire, climatic events, civil engineering)

Alberta Environment's weir safety program : options for rehabilitation to improve public safety : a case study of the Calgary weir

Energy Technology Data Exchange (ETDEWEB)

Blakely, D. [Alberta Environment, Edmonton, AB (Canada)

2009-07-01

Alberta Environment Water Management Operations (WMO) owns and operates 46 dams and 800 kilometres of canals in Alberta. The WMO consists of 120 staff and several contract operators to take care of this infrastructure. Most of the infrastructure supplies water for irrigation use, which adds 5 billion dollars to the provincial economy annually. Other water uses include stock watering, domestic use, municipal use, recreational use and habitat. Alberta Environment's weir safety program was also discussed along with options for rehabilitation to improve public safety. A case study of Calgary's Weir Dam on the Bow River was highlighted. A brief history of the dam was offered and safety programs around provincially-owned weirs were discussed. Photographs were included to illustrate some of the additional safety measures at the Calgary weir, such as suspended safety buoys upstream of the boom directing paddlers to the portage trail, and signage on the river that can be activated when the boom is out. Typical river users on the Calgary Bow River and safety history at the Calgary Weir were discussed along with other topics such as the Calgary Bow River weir project criteria; project design progress; pre-feasibility options; scale modelling; final design analysis; construction funding; and proposed changes to the safety program for the new weir configuration. figs.

The association between EMS workplace safety culture and safety outcomes.

Science.gov (United States)

Weaver, Matthew D; Wang, Henry E; Fairbanks, Rollin J; Patterson, Daniel

2012-01-01

Prior studies have highlighted wide variation in emergency medical services (EMS) workplace safety culture across agencies. To determine the association between EMS workplace safety culture scores and patient or provider safety outcomes. We administered a cross-sectional survey to EMS workers affiliated with a convenience sample of agencies. We recruited these agencies from a national EMS management organization. We used the EMS Safety Attitudes Questionnaire (EMS-SAQ) to measure workplace safety culture and the EMS Safety Inventory (EMS-SI), a tool developed to capture self-reported safety outcomes from EMS workers. The EMS-SAQ provides reliable and valid measures of six domains: safety climate, teamwork climate, perceptions of management, working conditions, stress recognition, and job satisfaction. A panel of medical directors, emergency medical technicians and paramedics, and occupational epidemiologists developed the EMS-SI to measure self-reported injury, medical errors and adverse events, and safety-compromising behaviors. We used hierarchical linear models to evaluate the association between EMS-SAQ scores and EMS-SI safety outcome measures. Sixteen percent of all respondents reported experiencing an injury in the past three months, four of every 10 respondents reported an error or adverse event (AE), and 89% reported safety-compromising behaviors. Respondents reporting injury scored lower on five of the six domains of safety culture. Respondents reporting an error or AE scored lower for four of the six domains, while respondents reporting safety-compromising behavior had lower safety culture scores for five of the six domains. Individual EMS worker perceptions of workplace safety culture are associated with composite measures of patient and provider safety outcomes. This study is preliminary evidence of the association between safety culture and patient or provider safety outcomes.

Safety culture in a pharmacy setting using a pharmacy survey on patient safety culture: a cross-sectional study in China.

Science.gov (United States)

Jia, P L; Zhang, L H; Zhang, M M; Zhang, L L; Zhang, C; Qin, S F; Li, X L; Liu, K X

2014-06-30

To explore the attitudes and perceptions of patient safety culture for pharmacy workers in China by using a Pharmacy Survey on Patient Safety Culture (PSOPSC), and to assess the psychometric properties of the translated Chinese language version of the PSOPSC. Cross-sectional study. Data were obtained from 20 hospital pharmacies in the southwest part of China. We performed χ(2) test to explore the differences on pharmacy staff in different hospital and qualification levels and countries towards patient safety culture. We also computed descriptive statistics, internal consistency coefficients and intersubscale correlation analysis, and then conducted an exploratory factor analysis. A test-retest was performed to assess reproducibility of the items. A total of 630 questionnaires were distributed of which 527 were responded to validly (response rate 84%). The positive response rate for each item ranged from 37% to 90%. The positive response rate on three dimensions ('Teamwork', 'Staff Training and Skills' and 'Staffing, Work Pressure and Pace') was higher than that of Agency for Healthcare Research and Quality (AHRQ) data (pculture at different hospital and qualification levels. The internal consistency of the total survey was comparatively satisfied (Cronbach's α=0.89). The results demonstrated that among the pharmacy staffs surveyed in China, there was a positive attitude towards patient safety culture in their organisations. Identifying perspectives of patient safety culture from pharmacists in different hospital and qualification levels are important, since this can help support decisions about action to improve safety culture in pharmacy settings. The Chinese translation of the PSOPSC questionnaire (V.2012) applied in our study is acceptable. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://group.bmj.com/group/rights-licensing/permissions.

Studies on environment safety and application of advanced reactor for inland nuclear power plants

International Nuclear Information System (INIS)

Wei, L.; Jie, L.

2014-01-01

To study environment safety assessment of inland nuclear power plants (NPPs), the impact of environment safety under the normal operation was researched and the environment risk of serious accidents was analyzed. Moreover, the requirements and relevant provisions of site selection between international nuclear power plant and China's are comparatively studied. The conclusion was that the environment safety assessment of inland and coastal nuclear power plant have no essential difference; the advanced reactor can meet with high criteria of environment safety of inland nuclear power plants. In this way, China is safe and feasible to develop inland nuclear power plant. China's inland nuclear power plants will be as big market for advanced reactor. (author)

Indicators of Faculty and Staff Perceptions of Campus Safety: A Case Study

Science.gov (United States)

Woolfolk, Willie A.

2013-01-01

The study addressed the problem of a critical increase in campus crime between 1999 and 2009, a period during which overall crime in the United States declined. Further the research explored the perceptions of campus safety among faculty and staff at an institution where campus safety initiatives are nationally ranked as exemplary and incidents of…

Present status of nuclear power safety studies in JAERI

International Nuclear Information System (INIS)

1989-01-01

Japan Atomic Energy Research Institute carries out the safety research required for ensuring safety accompanying the development and utilization of atomic energy, dividing the roles with industrial circules, universities and other public research institutes. First, it carries out the research based on the yearly program of safety research, in which the subjects of safety research that the state should execute are decided. Next, it carries out a series of the safety verification test on atomic energy facilities entrusted by the state using the special account for power source development promotion countermeasures. Besides, it carries out the safety research on the specific subjects entrusted by outside organizations. The object and range of atomic energy safety at present are roughly divided into four fields, that is, nuclear power stations, nuclear fuel facilities, waste treatment and disposal, and environmental radioactivity. In order to advance the research effectively, in addition to the generalization department and the execution department, various committees are organized. In 1988, about 260 persons engaged in these four research fields, and the budget for fiscal year 1988 was about 17.4 billion yen. (K.I.)

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

Science.gov (United States)

2010-09-29

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

Thermal safety of ultrasound-enhanced ocular drug delivery: A modeling study

Energy Technology Data Exchange (ETDEWEB)

Nabili, Marjan, E-mail: mnabili@gwmail.gwu.edu [Department of Electrical and Computer Engineering, The George Washington University, 800 22nd Street NW, Room 5000, Washington, DC 20052 (United States); Geist, Craig, E-mail: cgeist@mfa.gwu.edu, E-mail: zderic@gwu.edu [Department of Ophthalmology, The George Washington University, 2150 Pennsylvania Avenue NW, Floor 2A, Washington, DC 20037 (United States); Zderic, Vesna, E-mail: cgeist@mfa.gwu.edu, E-mail: zderic@gwu.edu [Department of Biomedical Engineering, The George Washington University, 800 22nd Street NW, Room 6670, Washington, DC 20052 (United States)

2015-10-15

Purpose: Delivery of sufficient amounts of therapeutic drugs into the eye for treatment of various ocular diseases is often a challenging task. Ultrasound was shown to be effective in enhancing ocular drug delivery in the authors’ previous in vitro and in vivo studies. Methods: The study reported here was designed to investigate the safety of ultrasound application and its potential thermal effects in the eye using PZFlex modeling software. The safety limit in this study was set as a temperature increase of no more than 1.5 °C based on regulatory recommendations and previous experimental safety studies. Acoustic and thermal specifications of different human eye tissues were obtained from the published literature. The tissues of particular interest in this modeling safety study were cornea, lens, and the location of optic nerve in the posterior eye. Ultrasound application was modeled at frequencies of 400 kHz–1 MHz, intensities of 0.3–1 W/cm{sup 2}, and exposure duration of 5 min, which were the parameters used in the authors’ previous drug delivery experiments. The baseline eye temperature was 37 °C. Results: The authors’ results showed that the maximal tissue temperatures after 5 min of ultrasound application were 38, 39, 39.5, and 40 °C in the cornea, 39.5, 40, 42, and 43 °C in the center of the lens, and 37.5, 38.5, and 39 °C in the back of the eye (at the optic nerve location) at frequencies of 400, 600, 800 kHz, and 1 MHz, respectively. Conclusions: The ocular temperatures reached at higher frequencies were considered unsafe based on current recommendations. At a frequency of 400 kHz and intensity of 0.8 W/cm{sup 2} (parameters shown in the authors’ previous in vivo studies to be optimal for ocular drug delivery), the temperature increase was small enough to be considered safe inside different ocular tissues. However, the impact of orbital bone and tissue perfusion should be included in future modeling efforts to determine the safety

Thermal safety of ultrasound-enhanced ocular drug delivery: A modeling study

International Nuclear Information System (INIS)

Nabili, Marjan; Geist, Craig; Zderic, Vesna

2015-01-01

Purpose: Delivery of sufficient amounts of therapeutic drugs into the eye for treatment of various ocular diseases is often a challenging task. Ultrasound was shown to be effective in enhancing ocular drug delivery in the authors’ previous in vitro and in vivo studies. Methods: The study reported here was designed to investigate the safety of ultrasound application and its potential thermal effects in the eye using PZFlex modeling software. The safety limit in this study was set as a temperature increase of no more than 1.5 °C based on regulatory recommendations and previous experimental safety studies. Acoustic and thermal specifications of different human eye tissues were obtained from the published literature. The tissues of particular interest in this modeling safety study were cornea, lens, and the location of optic nerve in the posterior eye. Ultrasound application was modeled at frequencies of 400 kHz–1 MHz, intensities of 0.3–1 W/cm 2 , and exposure duration of 5 min, which were the parameters used in the authors’ previous drug delivery experiments. The baseline eye temperature was 37 °C. Results: The authors’ results showed that the maximal tissue temperatures after 5 min of ultrasound application were 38, 39, 39.5, and 40 °C in the cornea, 39.5, 40, 42, and 43 °C in the center of the lens, and 37.5, 38.5, and 39 °C in the back of the eye (at the optic nerve location) at frequencies of 400, 600, 800 kHz, and 1 MHz, respectively. Conclusions: The ocular temperatures reached at higher frequencies were considered unsafe based on current recommendations. At a frequency of 400 kHz and intensity of 0.8 W/cm 2 (parameters shown in the authors’ previous in vivo studies to be optimal for ocular drug delivery), the temperature increase was small enough to be considered safe inside different ocular tissues. However, the impact of orbital bone and tissue perfusion should be included in future modeling efforts to determine the safety of this

Consideration of future safety consequences: a new predictor of employee safety.

Science.gov (United States)

Probst, Tahira M; Graso, Maja; Estrada, Armando X; Greer, Sarah

2013-06-01

Compliance with safety behaviors is often associated with longer term benefits, but may require some short-term sacrifices. This study examines the extent to which consideration of future safety consequences (CFSC) predicts employee safety outcomes. Two field studies were conducted to evaluate the reliability and validity of the newly developed Consideration of Future Safety Consequences (CFSC) scale. Surveys containing the CFSC scale and other measures of safety attitudes, behaviors, and outcomes were administered during working hours to a sample of 128 pulp and paper mill employees; after revising the CFSC scale based on these initial results, follow-up survey data were collected in a second sample of 212 copper miners. In Study I, CFSC was predictive of employee safety knowledge and motivation, compliance, safety citizenship behaviors, accident reporting attitudes and behaviors, and workplace injuries - even after accounting for conscientiousness and demographic variables. Moreover, the effects of CFSC on the variables generally appear to be direct, as opposed to mediated by safety knowledge or motivation. These findings were largely replicated in Study II. CFSC appears to be an important personality construct that may predict those individuals who are more likely to comply with safety rules and have more positive safety outcomes. Future research should examine the longitudinal stability of CFSC to determine the extent to which this construct is a stable trait, rather than a safety attitude amenable to change over time or following an intervention. Copyright © 2013 Elsevier Ltd. All rights reserved.

Strong movement data currently available at IPSN/DAS

International Nuclear Information System (INIS)

Hamaide, D.; Mohammadioun, B.; Mohammadioun, G.

1986-01-01

The collection of recordings and other data on strong seismic motion compiled by the Departement d'Analyse de Surete de l'Institut de Protection et de Surete Nucleaire (Commissariat a l'Energie Atomique) to form a data base known as ''sismotheque'' are presented. Following an introduction wherein the necessity of creating such a repertory for evaluating seismic hazard on the sites of nuclear facilities is explained, a description is given of the means engaged, i.e. motion recorded by the DAS's own laboratory or data procured from other research units in France or abroad. The quantity and quality of the data now available are summarized, as well as the techniques designed to gain access to desired information, illustrated by concrete examples. The paper concludes with recommendations for future developments [fr

Patient safety priorities in mental healthcare in Switzerland: a modified Delphi study.

Science.gov (United States)

Mascherek, Anna C; Schwappach, David L B

2016-08-05

Identifying patient safety priorities in mental healthcare is an emerging issue. A variety of aspects of patient safety in medical care apply for patient safety in mental care as well. However, specific aspects may be different as a consequence of special characteristics of patients, setting and treatment. The aim of the present study was to combine knowledge from the field and research and bundle existing initiatives and projects to define patient safety priorities in mental healthcare in Switzerland. The present study draws on national expert panels, namely, round-table discussion and modified Delphi consensus method. As preparation for the modified Delphi questionnaire, two round-table discussions and one semistructured questionnaire were conducted. Preparative work was conducted between May 2015 and October 2015. The modified Delphi was conducted to gauge experts' opinion on priorities in patient safety in mental healthcare in Switzerland. In two independent rating rounds, experts made private ratings. The modified Delphi was conducted in winter 2015. Nine topics were defined along the treatment pathway: diagnostic errors, non-drug treatment errors, medication errors, errors related to coercive measures, errors related to aggression management against self and others, errors in treatment of suicidal patients, communication errors, errors at interfaces of care and structural errors. Patient safety is considered as an important topic of quality in mental healthcare among experts, but it has been seriously neglected up until now. Activities in research and in practice are needed. Structural errors and diagnostics were given highest priority. From the topics identified, some are overlapping with important aspects of patient safety in medical care; however, some core aspects are unique. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://www.bmj.com/company/products-services/rights-and-licensing/

A review on food safety and food hygiene studies in Ghana

OpenAIRE

Ababio, P. F.; Lovatt, P.

2015-01-01

Food safety and hygiene in Ghana was studied using desk top literature review. Food research was highly concentrated in the capital city of the country and most research focus were on commercial food operations specifically street foods and microbiological safety with limited information from institutional catering and other forms of food hazards. The media currently serves as the main source for reporting of food borne diseases. Food establishments and other sources contributing to food born...

Healthcare databases in Europe for studying medicine use and safety during pregnancy

DEFF Research Database (Denmark)

Charlton, Rachel A; Neville, Amanda J; Jordan, Sue

2014-01-01

data recorded by primary-care practitioners. All databases captured maternal co-prescribing and a measure of socioeconomic status. CONCLUSION: This study suggests that within Europe, electronic healthcare databases may be valuable sources of data for evaluating medicine use and safety during pregnancy......PURPOSE: The aim of this study was to describe a number of electronic healthcare databases in Europe in terms of the population covered, the source of the data captured and the availability of data on key variables required for evaluating medicine use and medicine safety during pregnancy. METHODS....... The suitability of a particular database, however, will depend on the research question, the type of medicine to be evaluated, the prevalence of its use and any adverse outcomes of interest. © 2014 The Authors. Pharmacoepidemiology and Drug Safety published by John Wiley & Sons, Ltd....

Sun Safety at Work Canada: a multiple case-study protocol to develop sun safety and heat protection programs and policies for outdoor workers.

Science.gov (United States)

Kramer, Desre M; Tenkate, Thomas; Strahlendorf, Peter; Kushner, Rivka; Gardner, Audrey; Holness, D Linn

2015-07-10

CAREX Canada has identified solar ultraviolet radiation (UV) as the second most prominent carcinogenic exposure in Canada, and over 75 % of Canadian outdoor workers fall within the highest exposure category. Heat stress also presents an important public health issue, particularly for outdoor workers. The most serious form of heat stress is heat stroke, which can cause irreversible damage to the heart, lungs, kidneys, and liver. Although the need for sun and heat protection has been identified, there is no Canada-wide heat and sun safety program for outdoor workers. Further, no prevention programs have addressed both skin cancer prevention and heat stress in an integrated approach. The aim of this partnered study is to evaluate whether a multi-implementation, multi-evaluation approach can help develop sustainable workplace-specific programs, policies, and procedures to increase the use of UV safety and heat protection. This 2-year study is a theory-driven, multi-site, non-randomized study design with a cross-case analysis of 13 workplaces across four provinces in Canada. The first phase of the study includes the development of workplace-specific programs with the support of the intensive engagement of knowledge brokers. There will be a three-points-in-time evaluation with process and impact components involving the occupational health and safety (OHS) director, management, and workers with the goal of measuring changes in workplace policies, procedures, and practices. It will use mixed methods involving semi-structured key informant interviews, focus groups, surveys, site observations, and UV dosimetry assessment. Using the findings from phase I, in phase 2, a web-based, interactive, intervention planning tool for workplaces will be developed, as will the intensive engagement of intermediaries such as industry decision-makers to link to policymakers about the importance of heat and sun safety for outdoor workers. Solar UV and heat are both health and safety hazards

Investigations concerning fire-induced accidents in nuclear facilities

International Nuclear Information System (INIS)

Lamuth, P.; Lernout, L.A.; Bonneval, F.; Cottaz, M.

1996-01-01

In the context of fire protection in technical buildings of French nuclear facilities, three principles have been adopted: prevention, detection and fire-fighting. Their implementation makes it possible on the one hand to limit the fire ignition and the fire growth, and on the other hand to prevent fire extent which would lead to unavailability of several safety related equipment. Although progress has been made in this direction, the fire risks have still not been eliminated. It is therefore essential to evaluate the fire effects and to assess their consequences. To this end, three main R and D programs have been conducted into fires. Part I sets out the fire PSA methodology used for a 900 MWe PWR. Part II gives an outline of two fire and ventilation computer codes useful for the fire PSA. Finally, part III gives an outline of the tests already performed and those currently under way in the two laboratories of the Institut de Protection et de Surete Nucleaire (IPSN) in order to qualify the codes and provide useful information for the safety assessment. (author)

Safety Study of Doxicycline in Broiler Chickens

Directory of Open Access Journals (Sweden)

Romeo Teodor Cristina

2010-05-01

Full Text Available Doxicycline is a structural isomer who meets the European reference standard (Ph.Eur. III 1997:0272 and respect EU Regulations for M.R.L. The good solubility permits high tissular absorption and distribution after administration in drinking water. The aim was to ascertain the clinical effects and tolerance consecutive to risen doses administration, as a part of safety study for this antibiotic in poultry in the respect of current drug testing methodology. The safety study revealed: good local and general tolerance to therapeutic doses (10 mg x kgb.w.-1 and to x2 dose, diarrhoea in lots which received x3 and x5 the therapeutic dose. Comparatively with the Control lot, haemoleucogram doesn’t suffer evident changes the registered values being between the references limits (exception of leucocitary formula. Also it was found an increased creatinin concentration consecutively to x3 and x5 greater doses administration and marked increasing of ASAT level and limited for ALAT’s, comparatively to control lot in the case of E4 lot, but light to reference values. Macro and microscopy revealed for the liver samples: hepatomegaly, diffuse hepatic degenerescence, nuclear heterochromatinization, vacuolar degenerescence; renal changes in nefrons and renal corpuscles, light splenomegaly, caecal sacs distension and brown-yellowish gaseous content to lots E3 and E4.

A Study of Time Response for Safety-Related Operator Actions in Non-LOCA Safety Analysis

Energy Technology Data Exchange (ETDEWEB)

Lee, Min Seok; Lee, Sang Seob; Park, Min Soo; Lee, Gyu Cheon; Kim, Shin Whan [KEPCO E and C Company, Daejeon (Korea, Republic of)

2014-10-15

The classification of initiating events for safety analysis report (SAR) chapter 15 is categorized into moderate frequency events (MF), infrequent events (IF), and limiting faults (LF) depending on the frequency of its occurrence. For the non-LOCA safety analysis with the purpose to get construction or operation license, however, it is assumed that the operator response action to mitigate the events starts at 30 minutes after the initiation of the transient regardless of the event categorization. Such an assumption of corresponding operator response time may have over conservatism with the MF and IF events and results in a decrease in the safety margin compared to its acceptance criteria. In this paper, the plant conditions (PC) are categorized with the definitions in SAR 15 and ANS 51.1. Then, the consequence of response for safety-related operator action time is determined based on the PC in ANSI 58.8. The operator response time for safety analysis regarding PC are reviewed and suggested. The clarifying alarm response procedure would be required for the guideline to reduce the operator response time when the alarms indicate the occurrence of the transient.

A cross-cultural study of organizational factors on safety: Japanese vs. Taiwanese oil refinery plants.

Science.gov (United States)

Hsu, Shang Hwa; Lee, Chun-Chia; Wu, Muh-Cherng; Takano, Kenichi

2008-01-01

This study attempts to identify idiosyncrasies of organizational factors on safety and their influence mechanisms in Taiwan and Japan. Data were collected from employees of Taiwanese and Japanese oil refinery plants. Results show that organizational factors on safety differ in the two countries. Organizational characteristics in Taiwanese plants are highlighted as: higher level of management commitment to safety, harmonious interpersonal relationship, more emphasis on safety activities, higher devotion to supervision, and higher safety self-efficacy, as well as high quality of safety performance. Organizational characteristics in Japanese plants are highlighted as: higher level of employee empowerment and attitude towards continuous improvement, more emphasis on systematic safety management approach, efficient reporting system and teamwork, and high quality of safety performance. The casual relationships between organizational factors and workers' safety performance were investigated using structural equation modeling (SEM). Results indicate that the influence mechanisms of organizational factors in Taiwan and Japan are different. These findings provide insights into areas of safety improvement in emerging countries and developed countries respectively.

Present status of nuclear power safety studies in JAERI, 1994

International Nuclear Information System (INIS)

1994-10-01

Securing safety in the development and utilization of nuclear power is the prerequisite, and in order to maintain the safety of nuclear power facilities at level corresponding to the expansion and diversification of nuclear power development and utilization, it is necessary to promote the safety research. The reliable evaluation of environmental effect and the safe disposal of radioactive waste are the indispensable conditions. Japan Atomic Energy Research Institute has carried out the research on the engineering safety of nuclear reactors and nuclear fuel cycle facilities and the research on the environmental safety related to environmental radiation and the treatment and disposal of radioactive waste. In this book, the researches on the safety of reactor fuel, the reliability of reactor machinery and equipment and structures, the thermo-hydraulic behavior of reactors at the time of accidents, the behavior of reactors at the time of severe accidents, the analytical research on the safety of reactors, the researches on the safety of nuclear fuel cycle, the treatment and disposal of radioactive waste, the assessment and analysis of environmental radiation and radioactivity, and the individual researches related to nuclear power safety are reported. (K.I.)

LMFBR conceptual design study: an overview of environmental and safety concerns

International Nuclear Information System (INIS)

Brenchley, D.L.

1981-06-01

The US Department of Energy (DOE) initiated the Liquid Metal Fast Breeder (LMFBR) Conceptual Design Study (CDS) with the objective of maintaining a viable breeder option. The project is scheduled to be completed in FY-1981 but decisions regarding plant construction will be delayed until at least 1985. This report provides a review of the potential environmental and safety engineering concerns for the CDS and recommends specific action for the Environmental and Safety Engineering Division of DOE

Study of radiation safety education practices in acute care Texas hospitals

International Nuclear Information System (INIS)

Lemley, A.A.; Hedl, J.J. Jr.; Griffin, E.E.

1987-01-01

A survey study was performed to assess the extent of radiation safety education and training in acute care Texas hospitals for radiologic technologists and other hospital personnel. The findings revealed a self-perceived need by hospital administrative personnel and were interpreted to suggest a quantitative need for increased radiation safety education for several classes of hospital personnel. The findings are discussed relative to potential certification requirements for technologists and implications for the training of other personnel

LMFBR conceptual design study: an overview of environmental and safety concerns

Energy Technology Data Exchange (ETDEWEB)

Brenchley, D.L.

1981-06-01

The US Department of Energy (DOE) initiated the Liquid Metal Fast Breeder (LMFBR) Conceptual Design Study (CDS) with the objective of maintaining a viable breeder option. The project is scheduled to be completed in FY-1981 but decisions regarding plant construction will be delayed until at least 1985. This report provides a review of the potential environmental and safety engineering concerns for the CDS and recommends specific action for the Environmental and Safety Engineering Division of DOE.

A Methodology To Incorporate The Safety Culture Into Probabilistic Safety Assessments

Energy Technology Data Exchange (ETDEWEB)

Park, Sunghyun; Kim, Namyeong; Jae, Moosung [Hanyang University, Seoul (Korea, Republic of)

2015-10-15

In order to incorporate organizational factors into PSA, a methodology needs to be developed. Using the AHP to weigh organizational factors as well as the SLIM to rate those factors, a methodology is introduced in this study. The safety issues related to nuclear safety culture have occurred increasingly. The quantification tool has to be developed in order to include the organizational factor into Probabilistic Safety Assessments. In this study, the state-of-the-art for the organizational evaluation methodologies has been surveyed. This study includes the research for organizational factors, maintenance process, maintenance process analysis models, a quantitative methodology using Analytic Hierarchy Process, Success Likelihood Index Methodology. The purpose of this study is to develop a methodology to incorporate the safety culture into PSA for obtaining more objective risk than before. The organizational factor considered in nuclear safety culture might affect the potential risk of human error and hardware-failure. The safety culture impact index to monitor the plant safety culture can be assessed by applying the developed methodology into a nuclear power plant.

A Methodology To Incorporate The Safety Culture Into Probabilistic Safety Assessments

International Nuclear Information System (INIS)

Park, Sunghyun; Kim, Namyeong; Jae, Moosung

2015-01-01

In order to incorporate organizational factors into PSA, a methodology needs to be developed. Using the AHP to weigh organizational factors as well as the SLIM to rate those factors, a methodology is introduced in this study. The safety issues related to nuclear safety culture have occurred increasingly. The quantification tool has to be developed in order to include the organizational factor into Probabilistic Safety Assessments. In this study, the state-of-the-art for the organizational evaluation methodologies has been surveyed. This study includes the research for organizational factors, maintenance process, maintenance process analysis models, a quantitative methodology using Analytic Hierarchy Process, Success Likelihood Index Methodology. The purpose of this study is to develop a methodology to incorporate the safety culture into PSA for obtaining more objective risk than before. The organizational factor considered in nuclear safety culture might affect the potential risk of human error and hardware-failure. The safety culture impact index to monitor the plant safety culture can be assessed by applying the developed methodology into a nuclear power plant

Transformational and passive leadership as cross-level moderators of the relationships between safety knowledge, safety motivation, and safety participation.

Science.gov (United States)

Jiang, Lixin; Probst, Tahira M

2016-06-01

While safety knowledge and safety motivation are well-established predictors of safety participation, less is known about the impact of leadership styles on these relationships. The purpose of the current study was to examine whether the positive relationships between safety knowledge and motivation and safety participation are contingent on transformational and passive forms of safety leadership. Using multilevel modeling with a sample of 171 employees nested in 40 workgroups, we found that transformational safety leadership strengthened the safety knowledge-participation relationship, whereas passive leadership weakened the safety motivation-participation relationship. Under low transformational leadership, safety motivation was not related to safety participation; under high passive leadership, safety knowledge was not related to safety participation. These results are discussed in light of organizational efforts to increase safety-related citizenship behaviors. Copyright © 2016 Elsevier Ltd and National Safety Council. All rights reserved.

Assessing the general safety and tolerability of vildagliptin: value of pooled analyses from a large safety database versus evaluation of individual studies

Directory of Open Access Journals (Sweden)

Schweizer A

2011-02-01

Full Text Available Anja Schweizer1, Sylvie Dejager2, James E Foley3, Wolfgang Kothny31Novartis Pharma AG, Basel, Switzerland; 2Novartis Pharma SAS, Rueil-Malmaison, France; 3Novartis Pharmaceuticals Corporation, East Hanover, NJ, USAAim: Analyzing safety aspects of a drug from individual studies can lead to difficult-to-interpret results. The aim of this paper is therefore to assess the general safety and tolerability, including incidences of the most common adverse events (AEs, of vildagliptin based on a large pooled database of Phase II and III clinical trials.Methods: Safety data were pooled from 38 studies of ≥12 to ≥104 weeks' duration. AE profiles of vildagliptin (50 mg bid; N = 6116 were evaluated relative to a pool of comparators (placebo and active comparators; N = 6210. Absolute incidence rates were calculated for all AEs, serious AEs (SAEs, discontinuations due to AEs, and deaths.Results: Overall AEs, SAEs, discontinuations due to AEs, and deaths were all reported with a similar frequency in patients receiving vildagliptin (69.1%, 8.9%, 5.7%, and 0.4%, respectively and patients receiving comparators (69.0%, 9.0%, 6.4%, and 0.4%, respectively, whereas drug-related AEs were seen with a lower frequency in vildagliptin-treated patients (15.7% vs 21.7% with comparators. The incidences of the most commonly reported specific AEs were also similar between vildagliptin and comparators, except for increased incidences of hypoglycemia, tremor, and hyperhidrosis in the comparator group related to the use of sulfonylureas.Conclusions: The present pooled analysis shows that vildagliptin was overall well tolerated in clinical trials of up to >2 years in duration. The data further emphasize the value of a pooled analysis from a large safety database versus assessing safety and tolerability from individual studies.Keywords: type 2 diabetes, dipeptidyl peptidase-4, edema, safety, vildagliptin

Environmental Health and Safety Status of Schools: Case Study in Paveh City of Kermanshah Province

Directory of Open Access Journals (Sweden)

Seyyed Alireza Mousavi

2017-10-01

Full Text Available Background & Aims of the Study: A most part of children time is spent in a school environment. Important part of the basic mission of schools is promoting the health and safety. So assessing the existing conditions is an important factor in promotion and this study conducted to investigate the environmental health and safety status of Paveh city schools in Kermanshah province. Materials & Methods: This is a descriptive-cross sectional study and has performed in Paveh city of Kermanshah province. The study population consisted of primary, secondary and high schools of Paveh city. Data has been collated by referring to schools, direct observation and completion of environmental health and safety checklist. Schools conditions were determined according to the environmental health and safety checklist in desirable, semi-desirable and undesirable. The collected data were analyzed using Excel software, and data means and frequencies sign in tables and were drawn by charts. Results: From the 28 schools have visited 35.6% of school building is old and 63.7% of school building is new built. In the study of all schools in 8% of schools environmental health status were undesirable and in 21% semi-desirable and in 71% were desirable, also safety status in 4% of all schools were undesirable  and in 21% semi-desirable and in 75% were desirable. Undesirable safety conditions related to adjacent to waste accumulation areas, brick buildings without footing beam, inappropriate distance of  first row bench from the boards, lack of green spaces Conclusion: Given the importance of safety in schools, more attention should be paid to this issue. It is essential to compliance with the principles of health and safety in schools, also any consideration and action in this field can be effective in reducing the risk of many related health problems.

Teaching microbiological food safety through case studies

Directory of Open Access Journals (Sweden)

Florence Dubois-Brissonnet

2015-10-01

Full Text Available Higher education students usually ask for more training based on case studies. This was addressed by designing a specific food safety module (24 hours in which students were shown how to predict microbiological risks in food products i.e. they were asked to determine product shelf-life according to product formulation, preservation methods and consumption habits using predictive microbiology tools. Working groups of four students first identified the main microbiological hazards associated with a specific product. To perform this task, they were given several documents including guides for good hygiene practices, reviews on microbiological hazards in the food sector, flow sheets, etc…  After three-hours of work, the working groups prepared and gave an oral presentation in front of their classmates and professors. This raised comments and discussion that allowed students to adjust their conclusions before beginning the next step of their work. This second step consisted in the evaluation of the safety risk associated with the two major microbiological hazards of the product studied, using predictive microbiology. Students then attended a general lecture on the different tools of predictive microbiology and tutorials (6 hours that made them familiar with the modelling of bacterial growth or inactivation. They applied these tools (9 hours to predict the shelf-life of the studied product according to various scenarios of preservation (refrigeration, water activity, concentration of salt or acid, modified atmosphere, etc… and/or consumption procedures (cooking. The module was concluded by oral presentations of each working group and included student evaluation (3 hours.

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

Science.gov (United States)

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

2012-07-27

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

Patients' evaluations of patient safety in English general practices: a cross-sectional study.

Science.gov (United States)

Ricci-Cabello, Ignacio; Marsden, Kate S; Avery, Anthony J; Bell, Brian G; Kadam, Umesh T; Reeves, David; Slight, Sarah P; Perryman, Katherine; Barnett, Jane; Litchfield, Ian; Thomas, Sally; Campbell, Stephen M; Doos, Lucy; Esmail, Aneez; Valderas, Jose M

2017-07-01

Description of safety problems and harm in general practices has previously relied on information from health professionals, with scarce attention paid to experiences of patients. To examine patient-reported experiences and outcomes of patient safety in primary care. Cross-sectional study in 45 general practices across five regions in the north, centre, and south of England. A version of the Patient Reported Experiences and Outcomes of Safety in Primary Care (PREOS-PC) questionnaire was sent to a random sample of 6736 patients. Main outcome measures included 'practice activation' (what a practice does to create a safe environment); 'patient activation' (how proactive are patients in ensuring safe healthcare delivery); 'experiences of safety events' (safety errors); 'outcomes of safety' (harm); and 'overall perception of safety' (how safe patients rate their practice). Questionnaires were returned by 1244 patients (18.4%). Scores were high for 'practice activation' (mean [standard error] = 80.4 out of 100 [2.0]) and low for 'patient activation' (26.3 out of 100 [2.6]). Of the patients, 45% reported experiencing at least one safety problem in the previous 12 months, mostly related to appointments (33%), diagnosis (17%), patient provider communication (15%), and coordination between providers (14%). Twenty-three per cent of the responders reported some degree of harm in the previous 12 months. The overall assessment of level of safety of practices was generally high (86.0 out of 100 [16.8]). Priority areas for patient safety improvement in general practices in England include appointments, diagnosis, communication, coordination, and patient activation. © British Journal of General Practice 2017.

A history of studies on safety of irradiated foods

International Nuclear Information System (INIS)

Miyahara, Makoto

2003-01-01

This report explained a history of studies on safety of irradiated foods in the United States. The army of USA had begun an experiment of irradiated foods in 1953. The toxic tests consisted of three phase, the phase I (1954 to 1959), phase II (1956 to 1965) and phase III (1971 to 1978). In the phase I, the short period toxic tests (90days) of 54 kinds of foods were carried out using high and low irradiation. The Swift and Company Laboratories reported detailed animal tests of 2685 albino rat, chickens and human. The animal tests showed many kinds of nutrition disorder, but the human test no problem. On phase II, 22 kinds of foods were tested for long period using rat, dog and mouse. Dog showed many kinds of symptom, for example, low birthrate, short life time, low growth rate, increasing spleen weight and thyroid disease. On phase III, two companies carried out the toxic test and Ralston Purina Company report is only data to be used now. Atomic Energy Commission (AEC) (1960 to 1970), Department of Commerce (1965 to 1976) and Department of Agriculture (1961 to 1966) studied safety of irradiated foods. Food and Drug Administration (FDA) determined that the irradiated foods belonged to under the category of food additive in 1958. FDA tests safety of irradiated foods using the determination tree and permitted many kinds of irradiated foods. (S.Y.)

Independent safety organization

International Nuclear Information System (INIS)

Kato, W.Y.; Weinstock, E.V.; Carew, J.F.; Cerbone, R.J.; Guppy, J.G.; Hall, R.E.; Taylor, J.H.

1985-01-01

Brookhaven National Laboratory has conducted a study on the need and feasibility of an independent organization to investigate significant safety events for the Office for Analysis and Evaluation of Operational Data, USNRC. The study consists of three parts: the need for an independent organization to investigate significant safety events, alternative organizations to conduct investigations, and legislative requirements. The determination of need was investigated by reviewing current NRC investigation practices, comparing aviation and nuclear industry practices, and interviewing a spectrum of representatives from the nuclear industry, the regulatory agency, and the public sector. The advantages and disadvantages of alternative independent organizations were studied, namely, an Office of Nuclear Safety headed by a director reporting to the Executive Director for Operations (EDO) of NRC; an Office of Nuclear Safety headed by a director reporting to the NRC Commissioners; a multi-member NTSB-type Nuclear Safety Board independent of the NRC. The costs associated with operating a Nuclear Safety Board were also included in the study. The legislative requirements, both new authority and changes to the existing NRC legislative authority, were studied. 134 references

Safety analysis fundamentals

International Nuclear Information System (INIS)

Wright, A.C.D.

2002-01-01

This paper discusses the safety analysis fundamentals in reactor design. This study includes safety analysis done to show consequences of postulated accidents are acceptable. Safety analysis is also used to set design of special safety systems and includes design assist analysis to support conceptual design. safety analysis is necessary for licensing a reactor, to maintain an operating license, support changes in plant operations

Status of the EU test blanket systems safety studies

International Nuclear Information System (INIS)

Panayotov, Dobromir; Poitevin, Yves; Ricapito, Italo; Zmitko, Milan

2015-01-01

Highlights: • TBS safety demonstration files. • Safety functions and related design features – detailed TBS components classifications. • Nuclear analyses, radiation shielding and protection. • TBS radiological waste management strategy and categorization. • Selection and definition of reference accidents scenarios and accidents analyses. - Abstract: The European joint undertaking for ITER and the development of fusion energy (‘Fusion for Energy’ – F4E) provides the European contributions to the ITER international fusion energy research project. Among others it includes also the development, design, technological demonstration and implementation of the European test blanket systems (TBS) in ITER. Currently two EU TBS designs are in the phase of conceptual design – helium-cooled lithium-lead (HCLL) and helium-cooled pebble-bed (HCPB). Safety demonstration is an important part of the work devoted to the achievement of the next key project milestone the conceptual design review. The paper reveals the details of the work on EU TBS safety performed in the last couple of years: update of the TBS safety demonstration files; safety functions and related design features; detailed TBS components classifications; nuclear analyses, radiation shielding and protection; TBS radiological waste management strategy and categorization; selection and definition of reference accidents scenarios, and accidents analyses. Finally the authors share the information on on-going and planned future EU TBS safety activities.

Status of the EU test blanket systems safety studies

Energy Technology Data Exchange (ETDEWEB)

Panayotov, Dobromir, E-mail: dobromir.panayotov@f4e.europa.eu; Poitevin, Yves; Ricapito, Italo; Zmitko, Milan

2015-10-15

Highlights: • TBS safety demonstration files. • Safety functions and related design features – detailed TBS components classifications. • Nuclear analyses, radiation shielding and protection. • TBS radiological waste management strategy and categorization. • Selection and definition of reference accidents scenarios and accidents analyses. - Abstract: The European joint undertaking for ITER and the development of fusion energy (‘Fusion for Energy’ – F4E) provides the European contributions to the ITER international fusion energy research project. Among others it includes also the development, design, technological demonstration and implementation of the European test blanket systems (TBS) in ITER. Currently two EU TBS designs are in the phase of conceptual design – helium-cooled lithium-lead (HCLL) and helium-cooled pebble-bed (HCPB). Safety demonstration is an important part of the work devoted to the achievement of the next key project milestone the conceptual design review. The paper reveals the details of the work on EU TBS safety performed in the last couple of years: update of the TBS safety demonstration files; safety functions and related design features; detailed TBS components classifications; nuclear analyses, radiation shielding and protection; TBS radiological waste management strategy and categorization; selection and definition of reference accidents scenarios, and accidents analyses. Finally the authors share the information on on-going and planned future EU TBS safety activities.

A study on Impact of Safety Culture on Safety Behavior: Moderating effect of Prevention Focus

Energy Technology Data Exchange (ETDEWEB)

Hwang, Sun Chul; Jung, Su Jin; Choi, Young Sung [KAERI, Daejeon (Korea, Republic of)

2016-05-15

In modern society, it has been acknowledged that disasters caused by civilization became inevitable. With growing attention to role of human as one component of the system to cope with accident to prevent disasters, various efforts have been deployed to keep safety. Most of the industries with high hazard have adopted the term as their banner in the efforts to promote safety in their installations and operations. Recently, the Fukushima nuclear power plants(NPPs) accident happened in Japan in 2011 resulted in great impact over the world and have highlighted the importance of safety culture again.

A study on Impact of Safety Culture on Safety Behavior: Moderating effect of Prevention Focus

International Nuclear Information System (INIS)

Hwang, Sun Chul; Jung, Su Jin; Choi, Young Sung

2016-01-01

In modern society, it has been acknowledged that disasters caused by civilization became inevitable. With growing attention to role of human as one component of the system to cope with accident to prevent disasters, various efforts have been deployed to keep safety. Most of the industries with high hazard have adopted the term as their banner in the efforts to promote safety in their installations and operations. Recently, the Fukushima nuclear power plants(NPPs) accident happened in Japan in 2011 resulted in great impact over the world and have highlighted the importance of safety culture again

Operator reliability study for Probabilistic Safety Analysis of an operating research reactor

International Nuclear Information System (INIS)

Mohamed, F.; Hassan, A.; Yahaya, R.; Rahman, I.; Maskin, M.; Praktom, P.; Charlie, F.

2015-01-01

Highlights: • Human Reliability Analysis (HRA) for Level 1 Probabilistic Safety Analysis (PSA) is performed on research nuclear reactor. • Implemented qualitative HRA framework is addressed. • Human Failure Events of significant impact to the reactor safety are derived. - Abstract: A Level 1 Probabilistic Safety Analysis (PSA) for the TRIGA Mark II research reactor of Malaysian Nuclear Agency has been developed to evaluate the potential risk in its operation. In conjunction to this PSA development, Human Reliability Analysis (HRA) is performed in order to determine human contribution to the risk. The aim of this study is to qualitatively analyze human actions (HAs) involved in the operation of this reactor according to the qualitative part of the HRA framework for PSA which is namely the identification, qualitative screening and modeling of HAs. By performing this framework, Human Failure Events (HFEs) of significant impact to the reactor safety are systematically analyzed and incorporated into the PSA structure. A part of the findings in this study will become the input for the subsequent quantitative part of the HRA framework, i.e. the Human Error Probability (HEP) quantification

Disentangling the roles of safety climate and safety culture: Multi-level effects on the relationship between supervisor enforcement and safety compliance.

Science.gov (United States)

Petitta, Laura; Probst, Tahira M; Barbaranelli, Claudio; Ghezzi, Valerio

2017-02-01

Despite increasing attention to contextual effects on the relationship between supervisor enforcement and employee safety compliance, no study has yet explored the conjoint influence exerted simultaneously by organizational safety climate and safety culture. The present study seeks to address this literature shortcoming. We first begin by briefly discussing the theoretical distinctions between safety climate and culture and the rationale for examining these together. Next, using survey data collected from 1342 employees in 32 Italian organizations, we found that employee-level supervisor enforcement, organizational-level safety climate, and autocratic, bureaucratic, and technocratic safety culture dimensions all predicted individual-level safety compliance behaviors. However, the cross-level moderating effect of safety climate was bounded by certain safety culture dimensions, such that safety climate moderated the supervisor enforcement-compliance relationship only under the clan-patronage culture dimension. Additionally, the autocratic and bureaucratic culture dimensions attenuated the relationship between supervisor enforcement and compliance. Finally, when testing the effects of technocratic safety culture and cooperative safety culture, neither safety culture nor climate moderated the relationship between supervisor enforcement and safety compliance. The results suggest a complex relationship between organizational safety culture and safety climate, indicating that organizations with particular safety cultures may be more likely to develop more (or less) positive safety climates. Moreover, employee safety compliance is a function of supervisor safety leadership, as well as the safety climate and safety culture dimensions prevalent within the organization. Copyright © 2016 Elsevier Ltd. All rights reserved.

Nuclear fuel safety studies by laser pulse heating

International Nuclear Information System (INIS)

Viswanadham, C.S.; Kumar, Santosh; Dey, G.K.; Kutty, T.R.G.; Khan, K.B.; Kumar, Arun; Jathar, V.P.; Sahoo, K.C.

2009-01-01

The behaviour of nuclear fuels under transient heating conditions is vital to nuclear safety. A laser pulse based heating system to simulate the transient heating conditions experienced by the fuel during reactor accidents like LOCA and RIA is under development at BARC, Mumbai. Some of the concepts used in this system are under testing in pilot studies. This paper describes the results of some pilot studies carried out on unirradiated UO 2 specimens by laser pulse heating, followed by metallography and X-ray diffraction measurements. (author)

Study on the operational safety performance indicator of nuclear power plants in China

International Nuclear Information System (INIS)

Zhou Shirong

2005-01-01

The operational Safety Performance Indicator system (SPI) has been more and more regarded recently for their clear and effective characteristic in safety assessment for Nuclear Power Plants (NPPs). A large developing plan for NPPs construction is being discussed and considered in P.R. China. As one of important nuclear country, China expects to ensure the normal operation of NPPs and improve the safety level. National Nuclear Safety Administration (NNSA), National Nuclear Regulatory Agency of China, has put high attention on safety and SPI area, and many endeavours and attempts have been done or being carried out for an establishment of SPI system in China. NNSA intends to build an integrated SPI system to monitor all of the NPPs operation in China, based on the SPI system currently used in the world. NNSA believes that the SPI system will help to more effectively enforce the function of surveillance and management. The paper will introduces the status of study on the operational safety performance indicator of Nuclear Power Plants in China. (author)

Strengthening leadership as a catalyst for enhanced patient safety culture: a repeated cross-sectional experimental study.

Science.gov (United States)

Kristensen, Solvejg; Christensen, Karl Bang; Jaquet, Annette; Møller Beck, Carsten; Sabroe, Svend; Bartels, Paul; Mainz, Jan

2016-05-13

Current literature emphasises that clinical leaders are in a position to enable a culture of safety, and that the safety culture is a performance mediator with the potential to influence patient outcomes. This paper aims to investigate staff's perceptions of patient safety culture in a Danish psychiatric department before and after a leadership intervention. A repeated cross-sectional experimental study by design was applied. In 2 surveys, healthcare staff were asked about their perceptions of the patient safety culture using the 7 patient safety culture dimensions in the Safety Attitudes Questionnaire. To broaden knowledge and strengthen leadership skills, a multicomponent programme consisting of academic input, exercises, reflections and discussions, networking, and action learning was implemented among the clinical area level leaders. In total, 358 and 325 staff members participated before and after the intervention, respectively. 19 of the staff members were clinical area level leaders. In both surveys, the response rate was >75%. The proportion of frontline staff with positive attitudes improved by ≥5% for 5 of the 7 patient safety culture dimensions over time. 6 patient safety culture dimensions became more positive (increase in mean) (pculture are remarkable, and imply that strengthening the leadership can act as a significant catalyst for patient safety culture improvement. Further studies using a longitudinal study design are recommended to investigate the mechanism behind leadership's influence on patient safety culture, sustainability of improvements over time, and the association of change in the patient safety culture measures with change in psychiatric patient safety outcomes. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://www.bmj.com/company/products-services/rights-and-licensing/

3D analysis methods - Study and seminar[BWR safety analysis

Energy Technology Data Exchange (ETDEWEB)

Daaviittila, A [Valtion Teknillinen Tutkimuskeskus (Finland)

2003-10-01

The first part of the report results from a study that was performed as a Nordic co-operation activity with active participation from Studsvik Scandpower and Westinghouse Atom in Sweden, and VTT in Finland. The purpose of the study was to identify and investigate the effects rising from using the 3D transient com-puter codes in BWR safety analysis, and their influence on the transient analysis methodology. One of the main questions involves the critical power ratio (CPR) calculation methodology. The present way, where the CPR calculation is per-formed with a separate hot channel calculation, can be artificially conservative. In the investigated cases, no dramatic minimum CPR effect coming from the 3D calculation is apparent. Some cases show some decrease in the transient change of minimum CPR with the 3D calculation, which confirms the general thinking that the 1D calculation is conservative. On the other hand, the observed effect on neutron flux behaviour is quite large. In a slower transient the 3D effect might be stronger. The second part of the report is a summary of a related seminar that was held on the 3D analysis methods. The seminar was sponsored by the Reactor Safety part (NKS-R) of the Nordic Nuclear Safety Research Programme (NKS). (au)

Assessing the general safety and tolerability of vildagliptin: value of pooled analyses from a large safety database versus evaluation of individual studies

Science.gov (United States)

Schweizer, Anja; Dejager, Sylvie; Foley, James E; Kothny, Wolfgang

2011-01-01

Aim: Analyzing safety aspects of a drug from individual studies can lead to difficult-to-interpret results. The aim of this paper is therefore to assess the general safety and tolerability, including incidences of the most common adverse events (AEs), of vildagliptin based on a large pooled database of Phase II and III clinical trials. Methods: Safety data were pooled from 38 studies of ≥12 to ≥104 weeks’ duration. AE profiles of vildagliptin (50 mg bid; N = 6116) were evaluated relative to a pool of comparators (placebo and active comparators; N = 6210). Absolute incidence rates were calculated for all AEs, serious AEs (SAEs), discontinuations due to AEs, and deaths. Results: Overall AEs, SAEs, discontinuations due to AEs, and deaths were all reported with a similar frequency in patients receiving vildagliptin (69.1%, 8.9%, 5.7%, and 0.4%, respectively) and patients receiving comparators (69.0%, 9.0%, 6.4%, and 0.4%, respectively), whereas drug-related AEs were seen with a lower frequency in vildagliptin-treated patients (15.7% vs 21.7% with comparators). The incidences of the most commonly reported specific AEs were also similar between vildagliptin and comparators, except for increased incidences of hypoglycemia, tremor, and hyperhidrosis in the comparator group related to the use of sulfonylureas. Conclusions: The present pooled analysis shows that vildagliptin was overall well tolerated in clinical trials of up to >2 years in duration. The data further emphasize the value of a pooled analysis from a large safety database versus assessing safety and tolerability from individual studies. PMID:21415917

Study of the Operational Safety of a Vascular Interventional Surgical Robotic System

Directory of Open Access Journals (Sweden)

Jian Guo

2018-03-01

Full Text Available This paper proposes an operation safety early warning system based on LabView (2014, National Instruments Corporation, Austin, TX, USA for vascular interventional surgery (VIS robotic system. The system not only provides intuitive visual feedback information for the surgeon, but also has a safety early warning function. It is well known that blood vessels differ in their ability to withstand stress in different age groups, therefore, the operation safety early warning system based on LabView has a vascular safety threshold function that changes in real-time, which can be oriented to different age groups of patients and a broader applicable scope. In addition, the tracing performance of the slave manipulator to the master manipulator is also an important index for operation safety. Therefore, we also transformed the slave manipulator and integrated the displacement error compensation algorithm in order to improve the tracking ability of the slave manipulator to the master manipulator and reduce master–slave tracking errors. We performed experiments “in vitro” to validate the proposed system. According to previous studies, 0.12 N is the maximum force when the blood vessel wall has been penetrated. Experimental results showed that the proposed operation safety early warning system based on LabView combined with operating force feedback can effectively avoid excessive collisions between the surgical catheter and vessel wall to avoid vascular puncture. The force feedback error of the proposed system is maintained between ±20 mN, which is within the allowable safety range and meets our design requirements. Therefore, the proposed system can ensure the safety of surgery.

Reports by the Parliamentary Office for scientific and technological assessments. Thursday, June 16, 2011. Transparency in nuclear safety; Comptes rendus de l' Office Parlementaire d'Evaluation des Choix Scientifiques et Technologiques. Jeudi 16 juin 2011. Transparence en matiere de surete nucleaire

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-06-15

In a first session dedicated to modalities of transparency in the field of nuclear safety, members of the French Parliament hear and discuss the interventions of representatives of the French nuclear safety authority (ASN), AREVA, EDF, the CEA, the French institute of radiation protection and nuclear safety (IRSN), of the High committee for transparency and information on nuclear safety (HCTISN). The second session addresses the improvement of transparency and comprised interventions by representatives of the OECD and of local commissions of information (ANCCLI)

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

Science.gov (United States)

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

2015-12-11

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

Patient safety climate profiles across time: Strength and level of safety climate associated with a quality improvement program in Switzerland—A cross-sectional survey study

Science.gov (United States)

Mascherek, Anna C.

2017-01-01

Safety Climate has been acknowledged as an unspecific factor influencing patient safety. However, studies rarely provide in-depth analysis of climate data. As a helpful approach, the concept of “climate strength” has been proposed. In the present study we tested the hypotheses that even if safety climate remains stable on mean-level across time, differences might be evident in strength or shape. The data of two hospitals participating in a large national quality improvement program were analysed for differences in climate profiles at two measurement occasions. We analysed differences on mean-level, differences in percent problematic response, agreement within groups, and frequency histograms in two large hospitals in Switzerland at two measurement occasions (2013 and 2015) applying the Safety Climate Survey. In total, survey responses of 1193 individuals were included in the analyses. Overall, small but significant differences on mean-level of safety climate emerged for some subgroups. Also, although agreement was strong at both time-points within groups, tendencies of divergence or consensus were present in both hospitals. Depending on subgroup and analyses chosen, differences were more or less pronounced. The present study illustrated that taking several measures into account and describing safety climate from different perspectives is necessary in order to fully understand differences and trends within groups and to develop interventions addressing the needs of different groups more precisely. PMID:28753633

Patient safety improvement programmes for primary care. Review of a Delphi procedure and pilot studies by the LINNEAUS collaboration on patient safety in primary care

Science.gov (United States)

Verstappen, Wim; Gaal, Sander; Esmail, Aneez; Wensing, Michel

2015-01-01

ABSTRACT Background: To improve patient safety it is necessary to identify the causes of patient safety incidents, devise solutions and measure the (cost-) effectiveness of improvement efforts. Objective: This paper provides a broad overview with practical guidance on how to improve patient safety. Methods: We used modified online Delphi procedures to reach consensus on methods to improve patient safety and to identify important features of patient safety management in primary care. Two pilot studies were carried out to assess the value of prospective risk analysis (PRA), as a means of identifying the causes of a patient safety incident. Results: A range of different methods can be used to improve patient safety but they have to be contextually specific. Practice organization, culture, diagnostic errors and medication safety were found to be important domains for further improvement. Improvement strategies for patient safety could benefit from insights gained from research on implementation of evidence-based practice. Patient involvement and prospective risk analysis are two promising and innovative strategies for improving patient safety in primary care. Conclusion: A range of methods is available to improve patient safety, but there is no ‘magic bullet.’ Besides better use of the available methods, it is important to use new and potentially more effective strategies, such as prospective risk analysis. PMID:26339837

A study on LAN applications in nuclear safety systems

International Nuclear Information System (INIS)

Kim, Sung; Lee, Young Ryul; Koo, Jun Mo; Han, Jai Bok

1995-01-01

It is a general tendency to digitalize the conventional relay based I and C systems in nuclear power plant. But, the digitalisation of nuclear safety systems has many a difficulty to surmount. The typical one thing of many difficulties is the data communication problem between local controllers and systems. The network architecture built with LAN (Local Area Network) in digital systems of the other industries are general. But in case of nuclear safety systems many considerations in point of safety and license are required to implement it in the field. In this parer, some considerations for applying LAN in nuclear safety systems were reviewed

Sensemaking and the co-production of safety: a qualitative study of primary medical care patients.

Science.gov (United States)

Rhodes, Penny; McDonald, Ruth; Campbell, Stephen; Daker-White, Gavin; Sanders, Caroline

2016-02-01

This study explores the ways in which patients make sense of 'safety' in the context of primary medical care. Drawing on qualitative interviews with primary care patients, we reveal patients' conceptualisation of safety as fluid, contingent, multi-dimensional, and negotiated. Participant accounts drew attention to a largely invisible and inaccessible (but taken for granted) architecture of safety, the importance of psycho-social as well as physical dimensions and the interactions between them, informal strategies for negotiating safety, and the moral dimension of safety. Participants reported being proactive in taking action to protect themselves from potential harm. The somewhat routinised and predictable nature of the primary medical care consultation, which is very different from 'one off' inpatient spells, meant that patients were not passive recipients of care. Instead they had a stock of accumulated knowledge and experience to inform their actions. In addition to highlighting the differences and similarities between hospital and primary care settings, the study suggests that a broad conceptualisation of patient safety is required, which encompasses the safety concerns of patients in primary care settings. © 2015 The Authors. Sociology of Health & Illness published by John Wiley & Sons Ltd on behalf of Foundation for SHIL.

Monitoring road safety development at regional level: A case study in the ASEAN region.

Science.gov (United States)

Chen, Faan; Wang, Jianjun; Wu, Jiaorong; Chen, Xiaohong; Zegras, P Christopher

2017-09-01

Persistent monitoring of progress, evaluating the results of interventions and recalibrating to achieve continuous improvement over time is widely recognized as being crucial towards the successful development of road safety. In the ASEAN (Association of Southeast Asian Nations) region there is a lack of well-resourced teams that contain multidisciplinary safety professionals, and specialists in individual countries, who are able to carry out this work effectively. In this context, not only must the monitoring framework be effective, it must also be easy to use and adapt. This paper provides a case study that can be easily reproduced; based on an updated and refined Road Safety Development Index (RSDI), by means of the RSR (Rank-sum ratio)-based model, for monitoring/reporting road safety development at regional level. The case study was focused on the road safety achievements in eleven Southeast Asian countries; identifying the areas of poor performance, potential problems and delays. These countries are finally grouped into several classes based on an overview of their progress and achievements regarding to road safety. The results allow the policymakers to better understand their own road safety progress toward their desired impact; more importantly, these results enable necessary interventions to be made in a quick and timely manner. Keeping action plans on schedule if things are not progressing as desired. This would avoid 'reinventing the wheel' and trial and error approaches to road safety, making the implementation of action plans more effective. Copyright © 2017 Elsevier Ltd. All rights reserved.

Safety sign designs for children by considering effect of the colors preferences: A case study

Science.gov (United States)

Iftadi, Irwan; Nugraha, Dian Cahya; Jauhari, Wakhid Ahmad

2018-02-01

Color has become a major consideration in ergonomics. Color conveys a message and it is an important element in safety signs. The importance of colors usage in safety sign designs makes the colors research into one of the things that must be done before designing them. So far, research in the related field only focused on the adult's perspective without involving children's perspective in designing the safety signs. This paper aims to find out how children's perception towards colors affects the safety sign designs. This study consist of eight sections which are literature study, direct observation, determining referents and other parameters, determining research respondents, making the booklet, assessing the colors preferences, determining the design's parameter value and creating the safety sign designs. Limitation of the research are the objects are the students with the age of 10 - 11 years old in Grade IV and then the research is conducted in the school day and hours that apply to the school. Chi square test and odds ratio are employed to assess the colors preferences. Twelve safety sign designs are proposed by considering the children's colors perception. The designs are grouped into three types of sign which are Mandatory Action Sign, Warning Sign and Prohibition Sign. Six colors are used to draw the safety signs i.e. red, orange, yellow, green, blue and black. On the basis of the study, it is concluded that the colors that often appears in safety signs is green with the percentage of 75% and that rarely appears is red with the percentage of 8.33%.

Using subcontractors: the experience of IRSN and INRS

International Nuclear Information System (INIS)

Jeffroy, Francois; Hery, Michel

2014-01-01

This article discusses the current status and assessment of risks and opportunities associated with subcontracting in nuclear installations as perceived and addressed by the IRSN (Institut de Radioprotection et de Surete Nucleaire) and the INRS (Institut National de Recherche et de Securite). A first part recalls how these issues have been addressed since the 1990's. The author notices that subcontracting is associated with different terminologies for the IRSN and the INRS. In the next part, the author discusses the debate about subcontracting. He outlines that the organisation of the client must be examined, notably with respect to safety, to the way ability and traceability of subcontractor activities are considered and addressed. He comments the relationships between the client and its subcontractors. He briefly comments how the IRSN and the INRS address differently these issues related to subcontracting

Study of the development of a safety culture by describing routine work

International Nuclear Information System (INIS)

Takagi, Miho; Maeda, Noriyuki; Iida, Hiroyasu

2017-01-01

In this study, we considered safety culture as how an organization and its employees pay attention to risks, and how it reduces them. Our study is based on Schein's model of organizational culture. The theory of organizational culture maintains that if we change level 1 (behavior), then level 3 (assumption) changes. We considered a method to foster a safety culture based on this theory. To begin, we described the routine work of an organization by using the functional resonance analysis method (FRAM). Then, we confirmed the risk reduction behaviors being done there. We found that it is necessary for the organization to be involved in a positive fashion to reduce risks, and we offered some behaviors that the organization can encourage during routine work. We thought that when these new behaviors become habits of organization members, the safety culture of the organization will be fostered. (author)

A distributed research network model for post-marketing safety studies: the Meningococcal Vaccine Study.

Science.gov (United States)

Velentgas, Priscilla; Bohn, Rhonda L; Brown, Jeffrey S; Chan, K Arnold; Gladowski, Patricia; Holick, Crystal N; Kramer, Judith M; Nakasato, Cynthia; Spettell, Claire M; Walker, Alexander M; Zhang, Fang; Platt, Richard

2008-12-01

We describe a multi-center post-marketing safety study that uses distributed data methods to minimize the need for covered entities to share protected health information (PHI). Implementation has addressed several issues relevant to creation of a large scale post-marketing drug safety surveillance system envisioned by the FDA's Sentinel Initiative. This retrospective cohort study of Guillain-Barré syndrome (GBS) following meningococcal conjugate vaccination incorporates the data and analytic expertise of five research organizations closely affiliated with US health insurers. The study uses administrative claims data, plus review of full text medical records to adjudicate the status of individuals with a diagnosis code for GBS (ICD9 357.0). A distributed network approach is used to create the analysis files and to perform most aspects of the analysis, allowing nearly all of the data to remain behind institutional firewalls. Pooled analysis files transferred to a central site will contain one record per person for approximately 0.2% of the study population, and contain PHI limited to the month and year of GBS onset for cases or the index date for matched controls. The first planned data extraction identified over 9 million eligible adolescents in the target age range of 11-21 years. They contributed an average of 14 months of eligible time on study over 27 months of calendar time. MCV4 vaccination coverage levels exceeded 20% among 17-18-year olds and 16% among 11-13 and 14-16-year-old age groups by the second quarter of 2007. This study demonstrates the feasibility of using a distributed data network approach to perform large scale post-marketing safety analyses and is scalable to include additional organizations and data sources. We believe these results can inform the development of a large national surveillance system. Copyright (c) 2008 John Wiley & Sons, Ltd.

Driving behaviours, traffic risk and road safety: comparative study between Malaysia and Singapore.

Science.gov (United States)

Khan, Saif ur Rehman; Khalifah, Zainab Binti; Munir, Yasin; Islam, Talat; Nazir, Tahira; Khan, Hashim

2015-01-01

The present study aims to investigate differences in road safety attitude, driver behaviour and traffic risk perception between Malaysia and Singapore. A questionnaire-based survey was conducted among a sample of Singaporean (n = 187) and Malaysian (n = 313) road users. The data was analysed using confirmatory factor analysis and structural equation modelling applied to measure comparative fit indices of Malaysian and Singaporean respondents. The results show that the perceived traffic risk of Malaysian respondents is higher than Singaporean counterparts. Moreover, the structural equation modelling has confirmed perceived traffic risk performing the role of full mediation between perceived driving skills and perceived road safety for both the countries, while perceived traffic skills was found to perform the role of partial mediation between aggression and anxiety, on one hand, and road safety, on the other hand, in Malaysia and Singapore. In addition, in both countries, a weak correlation between perceived driving skills, aggression and anxiety with perceived road safety was found, while a strong correlation exists with traffic risk perception. The findings of this study have been discussed in terms of theoretical, practical and conceptual implications for both scholars and policy-makers to better understand the young drivers' attitude and behaviour relationship towards road safety measures with a view to future research.

Driver characteristics associated with child safety seat usage in Malaysia: a cross-sectional study.

Science.gov (United States)

Kulanthayan, S; Razak, Ahmad; Schenk, Ellen

2010-03-01

The rapidly motorizing environment in Malaysia has made child occupant safety a current public health concern. The usage of child safety seats (CSS) is a widely regarded intervention to enhance child occupant safety, yet no study has been conducted on CSS in Malaysia. This study aims to determine the CSS usage rates in Malaysia and to assess driver characteristics that are associated with CSS usage. Nine variables - urban versus rural study location, age, gender, marital status, educational status, monthly family income, number of children present in the vehicle, distance traveled to the study location, and attitude - were examined through a cross-sectional study of interviewing drivers of 230 vehicles transporting at least one child safety in Malaysia. The results indicate that interventional efforts should focus on educational programs geared toward drivers that are less educated or extended family members who inconsistently transport young children. Furthermore, any educational efforts could be strongly enhanced by legislation mandating the use of CSS. Every effort should be made to thoroughly assess the effectiveness of any educational or legislative activities that are implemented. Copyright 2009 Elsevier Ltd. All rights reserved.

A study on safety assessment methodology for a vitrification plant

Energy Technology Data Exchange (ETDEWEB)

Seo, Y. C.; Lee, G. S.; Choi, Y. C.; Kim, G. H. [Yonsei Univ., Seoul (Korea, Republic of)

2002-03-15

In this study, the technical and regulatory status of radioactive waste vitrification technologies in foreign and domestic plants is investigated and analyzed, and then significant factors are suggested which must be contained in the final technical guideline or standard for the safety assessment of vitrification plants. Also, the methods to estimate the stability of vitrified waste forms are suggested with property analysis of them. The contents and scope of the study are summarized as follows : survey of the status on radioactive waste vitrification technologies in foreign and domestic plants, survey of the characterization methodology for radioactive waste form, analysis of stability for vitrified waste forms, survey and analysis of technical standards and regulations concerned with them in foreign and domestic plants, suggestion of significant factors for the safety assessment of vitrification plants, submission of regulated technical standard on radioactive waste vitrification plats.

A study on methodologies for assessing safety critical network's risk impact on Nuclear Power Plant

International Nuclear Information System (INIS)

Lim, T. J.; Lee, H. J.; Park, S. K.; Seo, S. J.

2006-08-01

The objectives of this project is to investigate and study existing reliability analysis techniques for communication networks in order to develop reliability analysis models for Nuclear Power Plant's safety-critical networks. It is necessary to make a comprehensive survey of current methodologies for communication network reliability. Major outputs of the first year study are design characteristics of safety-critical communication networks, efficient algorithms for quantifying reliability of communication networks, and preliminary models for assessing reliability of safety-critical communication networks

Premarket safety and efficacy studies for ADHD medications in children.

Directory of Open Access Journals (Sweden)

Florence T Bourgeois

Full Text Available Attention-deficit hyperactivity disorder (ADHD is a chronic condition and pharmacotherapy is the mainstay of treatment, with a variety of ADHD medications available to patients. However, it is unclear to what extent the long-term safety and efficacy of ADHD drugs have been evaluated prior to their market authorization. We aimed to quantify the number of participants studied and their length of exposure in ADHD drug trials prior to marketing.We identified all ADHD medications approved by the Food and Drug Administration (FDA and extracted data on clinical trials performed by the sponsor and used by the FDA to evaluate the drug's clinical efficacy and safety. For each ADHD medication, we measured the total number of participants studied and the length of participant exposure and identified any FDA requests for post-marketing trials.A total of 32 clinical trials were conducted for the approval of 20 ADHD drugs. The median number of participants studied per drug was 75 (IQR 0, 419. Eleven drugs (55% were approved after <100 participants were studied and 14 (70% after <300 participants. The median trial length prior to approval was 4 weeks (IQR 2, 9, with 5 (38% drugs approved after participants were studied <4 weeks and 10 (77% after <6 months. Six drugs were approved with requests for specific additional post-marketing trials, of which 2 were performed.Clinical trials conducted for the approval of many ADHD drugs have not been designed to assess rare adverse events or long-term safety and efficacy. While post-marketing studies can fill in some of the gaps, better assurance is needed that the proper trials are conducted either before or after a new medication is approved.

Food safety performance indicators to benchmark food safety output of food safety management systems.

Science.gov (United States)

Jacxsens, L; Uyttendaele, M; Devlieghere, F; Rovira, J; Gomez, S Oses; Luning, P A

2010-07-31

There is a need to measure the food safety performance in the agri-food chain without performing actual microbiological analysis. A food safety performance diagnosis, based on seven indicators and corresponding assessment grids have been developed and validated in nine European food businesses. Validation was conducted on the basis of an extensive microbiological assessment scheme (MAS). The assumption behind the food safety performance diagnosis is that food businesses which evaluate the performance of their food safety management system in a more structured way and according to very strict and specific criteria will have a better insight in their actual microbiological food safety performance, because food safety problems will be more systematically detected. The diagnosis can be a useful tool to have a first indication about the microbiological performance of a food safety management system present in a food business. Moreover, the diagnosis can be used in quantitative studies to get insight in the effect of interventions on sector or governmental level. Copyright 2010 Elsevier B.V. All rights reserved.

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.

Safety Aspects of Radioactive Waste Management in Different Nuclear Fuel Cycle Policies, a Comparative Study

International Nuclear Information System (INIS)

Gad Allah, A.A.

2009-01-01

With the increasing demand of energy worldwide, and due to the depletion of conventional natural energy resources, energy policies in many countries have been devoted to nuclear energy option. On the other hand, adopting a safe and reliable nuclear fuel cycle concept guarantees future nuclear energy sustain ability is a vital request from environmental and economic point of views. The safety aspects of radioactive waste management in the nuclear fuel cycle is a topic of great importance relevant to public acceptance of nuclear energy and the development of nuclear technology. As a part of nuclear fuel cycle safety evaluation studies in the department of nuclear fuel cycle safety, National Center for Nuclear Safety and Radiation Control (NCNSRC), this study evaluates the radioactive waste management policies and radiological safety aspects of three different nuclear fuel cycle policies. The once-through fuel cycle (OT- fuel cycle) or the direct spent fuel disposal concept for both pressurized light water reactor ( PWR) and pressurized heavy water reactor (PHWR or CANDU) systems and the s elf-generated o r recycling fuel cycle concept in PWR have been considered in the assessment. The environmental radiological safety aspects of different nuclear fuel cycle options have been evaluated and discussed throughout the estimation of radioactive waste generated from spent fuel from these fuel cycle options. The decay heat stored in the spent fuel was estimated and a comparative safety study between the three fuel cycle policies has been implemented

Understanding lean & safety projects: analysis of case studies

Directory of Open Access Journals (Sweden)

Maria Crema

2017-12-01

Full Text Available Facing the current socio-economic contingency while guaranteeing a high level of care quality is particularly challenging in the field of healthcare. Through an integrated adoption of emerging managerial solutions, projects that allow organizations to achieve both efficiency and patient safety improvements could be implemented, thereby transposing policy directives towards a safer and more sustainable healthcare system. Therefore, the purpose of this paper is to investigate the features of Lean & Safety (L&S projects. Three Health Lean Management (HLM projects that had unexpected patient safety results were selected from the same region. Differences and similarities among the cases have been highlighted and interesting points of evidence have been noted. Despite the fact that the projects were pursuing similar objectives and benefiting from comparable support, the obtained changes had direct impact on patient safety enhancement in the cases that involved the front-office processes, and an indirect impact on patient safely for the L&S project that focused on back-office activities. The implementation processes and the Information and Communication Technologies (ICT adoption of the cases are also different.

The influence of environmental conditions on safety management in hospitals: a qualitative study.

Science.gov (United States)

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

2018-05-02

Hospitals are confronted with increasing safety demands from a diverse set of stakeholders, including governmental organisations, professional associations, health insurance companies, patient associations and the media. However, little is known about the effects of these institutional and competitive pressures on hospital safety management. Previous research has shown that organisations generally shape their safety management approach along the lines of control- or commitment-based management. Using a heuristic framework, based on the contextually-based human resource theory, we analysed how environmental pressures affect the safety management approach used by hospitals. A qualitative study was conducted into hospital care in the Netherlands. Five hospitals were selected for participation, based on organisational characteristics as well as variation in their reputation for patient safety. We interviewed hospital managers and staff with a central role in safety management. A total of 43 semi-structured interviews were conducted with 48 respondents. The heuristic framework was used as an initial model for analysing the data, though new codes emerged from the data as well. In order to ensure safe care delivery, institutional and competitive stakeholders often impose detailed safety requirements, strong forces for compliance and growing demands for accountability. As a consequence, hospitals experience a decrease in the room to manoeuvre. Hence, organisations increasingly choose a control-based management approach to make sure that safety demands are met. In contrast, in case of more abstract safety demands and an organisational culture which favours patient safety, hospitals generally experience more leeway. This often results in a stronger focus on commitment-based management. Institutional and competitive conditions as well as strategic choices that hospitals make have resulted in various combinations of control- and commitment-based safety management. A balanced

ROAD ACCIDENT AND SAFETY STUDY IN SYLHET REGION OF BANGLADESH

Directory of Open Access Journals (Sweden)

B. K. BANIK

2011-08-01

Full Text Available Roads, highways and streets are fundamental infrastructure facilities to provide the transportation for passenger travel and goods movement from one place to another in Sylhet, north–eastern division of Bangladesh with rapid growth of road vehicle, being comparatively developed economic tourist prone area faces severe road traffic accident. Such severe road accidents cause harsh safety hazards on the roads of Sylhet area. This research work presents an overview of the road traffic accident and degraded road safety situation in Sylhet zone which in particular, discusses the key road accident problem characteristics identifying the hazardous roads and spots, most responsible vehicles and related components, conditions of drivers and pedestrians, most victims of accident, effects of accident on society, safety priorities and options available in Sylhet. In this regard, a comprehensive questionnaire survey was conducted on the concerned groups of transportation and detailed accident data was collected from a popular local newspaper. Analysis of the study reveals that Dhaka- Sylhet highway is the most hazardous in road basis and Sylhet Sador thana is the most vulnerable in thana basis in Sylhet region.

Safety Justification and Safety Case for Safety-critical Software in Digital Reactor Protection System

International Nuclear Information System (INIS)

Kwon, Kee-Choon; Lee, Jang-Soo; Jee, Eunkyoung

2016-01-01

Nuclear safety-critical software is under strict regulatory requirements and these regulatory requirements are essential for ensuring the safety of nuclear power plants. The verification & validation (V and V) and hazard analysis of the safety-critical software are required to follow regulatory requirements through the entire software life cycle. In order to obtain a license from the regulatory body through the development and validation of safety-critical software, it is essential to meet the standards which are required by the regulatory body throughout the software development process. Generally, large amounts of documents, which demonstrate safety justification including standard compliance, V and V, hazard analysis, and vulnerability assessment activities, are submitted to the regulatory body during the licensing process. It is not easy to accurately read and evaluate the whole documentation for the development activities, implementation technology, and validation activities. The safety case methodology has been kwon a promising approach to evaluate the level and depth of the development and validation results. A safety case is a structured argument, supported by a body of evidence that provides a compelling, comprehensible, and valid case that a system is safe for a given application in a given operating environment. It is suggested to evaluate the level and depth of the results of development and validation by applying safety case methodology to achieve software safety demonstration. A lot of documents provided as evidence are connected to claim that corresponds to the topic for safety demonstration. We demonstrated a case study in which more systematic safety demonstration for the target system software is performed via safety case construction than simply listing the documents

Safety Justification and Safety Case for Safety-critical Software in Digital Reactor Protection System

Energy Technology Data Exchange (ETDEWEB)

Kwon, Kee-Choon; Lee, Jang-Soo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Jee, Eunkyoung [KAIST, Daejeon (Korea, Republic of)

2016-10-15

Nuclear safety-critical software is under strict regulatory requirements and these regulatory requirements are essential for ensuring the safety of nuclear power plants. The verification & validation (V and V) and hazard analysis of the safety-critical software are required to follow regulatory requirements through the entire software life cycle. In order to obtain a license from the regulatory body through the development and validation of safety-critical software, it is essential to meet the standards which are required by the regulatory body throughout the software development process. Generally, large amounts of documents, which demonstrate safety justification including standard compliance, V and V, hazard analysis, and vulnerability assessment activities, are submitted to the regulatory body during the licensing process. It is not easy to accurately read and evaluate the whole documentation for the development activities, implementation technology, and validation activities. The safety case methodology has been kwon a promising approach to evaluate the level and depth of the development and validation results. A safety case is a structured argument, supported by a body of evidence that provides a compelling, comprehensible, and valid case that a system is safe for a given application in a given operating environment. It is suggested to evaluate the level and depth of the results of development and validation by applying safety case methodology to achieve software safety demonstration. A lot of documents provided as evidence are connected to claim that corresponds to the topic for safety demonstration. We demonstrated a case study in which more systematic safety demonstration for the target system software is performed via safety case construction than simply listing the documents.

Safety studies of plasma-wall events with AINA code for Japanese DEMO

Energy Technology Data Exchange (ETDEWEB)

Rivas, J.C., E-mail: jose.carlos.rivas@upc.edu [International Fusion Energy Research Centre (IFERC) (Japan); Fusion Energy Engineering Laboratory (FEEL), Technical University of Catalonia-BarcelonaTech (Spain); Nakamura, M.; Someya, Y.; Hoshino, K.; Asakura, N. [Japan Atomic Energy Agency (JAEA) (Japan); Takase, H. [International Fusion Energy Research Centre (IFERC) (Japan); Miyoshi, Y.; Utoh, H.; Tobita, K. [Japan Atomic Energy Agency (JAEA) (Japan); Dies, J.; Blas, A. de; Riego, A.; Fabbri, M. [Fusion Energy Engineering Laboratory (FEEL), Technical University of Catalonia-BarcelonaTech (Spain)

2016-11-01

Highlights: • Work done in AINA code during 2014 and 2015 at IFERC to develop a version for safety studies of a Japanese DEMO design. • A thermal model for a WCPB breeding blanket has been developed based in parametric input data from neutronics calculations. • A breakthrough for the safety studies of plasma-divertor transients: An integrated SOL-pedestal model + using melting time as objective variable + using optimization algorithm. • The results for the case of divertor show that both loss of plasma control (LOPC) transients and ex-vessel LOCA transient can induce severe melting. The difference is that while in the first case melting happens at PFC surface, in the second case it happens at copper heat sink. • Conclusions suggest that, because the minimum melting times are same order of magnitude than the energy confinement time, recovery time for plasma control system should be lower order. - Abstract: In this contribution, the work done in AINA code during 2014 and 2015 at IFERC is presented. The main motivation of this work was to adapt the code and to perform safety studies for a Japanese DEMO design. Related to AINA code, the work has supposed major changes in plasma models. Significant is the addition of an integrated SOL-pedestal model that allows the estimation of heat loads at divertor. Also, a thermal model for a WCPB (water cooled pebble bed) breeding blanket has been developed based in parametric input data from neutronics calculations. Related to safety studies, a major breakthrough in the study of LOPC (loss of plasma control) transients has been the use of an optimization method to determine the most severe transients in terms of the shortest melting times. The results of the safety study show that LOPC transients are not likely to be severe for breeding blanket, but for the case of divertor can induce severe melting. For ex-vessel LOCA (loss of coolant accident) analysis, it is severe for both blanket and divertor, but in the first case

Safety studies of plasma-wall events with AINA code for Japanese DEMO

International Nuclear Information System (INIS)

Rivas, J.C.; Nakamura, M.; Someya, Y.; Hoshino, K.; Asakura, N.; Takase, H.; Miyoshi, Y.; Utoh, H.; Tobita, K.; Dies, J.; Blas, A. de; Riego, A.; Fabbri, M.

2016-01-01

Highlights: • Work done in AINA code during 2014 and 2015 at IFERC to develop a version for safety studies of a Japanese DEMO design. • A thermal model for a WCPB breeding blanket has been developed based in parametric input data from neutronics calculations. • A breakthrough for the safety studies of plasma-divertor transients: An integrated SOL-pedestal model + using melting time as objective variable + using optimization algorithm. • The results for the case of divertor show that both loss of plasma control (LOPC) transients and ex-vessel LOCA transient can induce severe melting. The difference is that while in the first case melting happens at PFC surface, in the second case it happens at copper heat sink. • Conclusions suggest that, because the minimum melting times are same order of magnitude than the energy confinement time, recovery time for plasma control system should be lower order. - Abstract: In this contribution, the work done in AINA code during 2014 and 2015 at IFERC is presented. The main motivation of this work was to adapt the code and to perform safety studies for a Japanese DEMO design. Related to AINA code, the work has supposed major changes in plasma models. Significant is the addition of an integrated SOL-pedestal model that allows the estimation of heat loads at divertor. Also, a thermal model for a WCPB (water cooled pebble bed) breeding blanket has been developed based in parametric input data from neutronics calculations. Related to safety studies, a major breakthrough in the study of LOPC (loss of plasma control) transients has been the use of an optimization method to determine the most severe transients in terms of the shortest melting times. The results of the safety study show that LOPC transients are not likely to be severe for breeding blanket, but for the case of divertor can induce severe melting. For ex-vessel LOCA (loss of coolant accident) analysis, it is severe for both blanket and divertor, but in the first case

Occupational safety motivation

DEFF Research Database (Denmark)

Pedersen, Louise; Kines, Pete

2010-01-01

Background: Motivation is one of the most important factors for safety behaviour and for implementing change in general. However, theoretical and psychometric studies of safety performance have traditionally treated safety motivation, safety compliance and safety participation unidimensionally....... At the same time many motivation questionnaire items are seldom founded on theory and/or do not account for the theories’ ontological and epistemological differences, e.g. of how knowledge, attitude and action are related. Present questionnaire items tap into occupational safety motivation in asking whether...... or not respondents ‘are’ motivated and whether they feel that safety is important or worthwhile. Another important aspect is ‘what’ motivates workers to comply to and participate in safety. The aim of this article is to introduce a new theory-based occupational safety motivation scale which is validated...

Patient-reported safety incidents in older patients with long-term conditions: a large cross-sectional study.

Science.gov (United States)

Panagioti, Maria; Blakeman, Thomas; Hann, Mark; Bower, Peter

2017-05-30

Increasing evidence suggests that patient safety is a serious concern for older patients with long-term conditions. Despite this, there is a lack of research on safety incidents encountered by this patient group. In this study, we sought to examine patient reports of safety incidents and factors associated with reports of safety incidents in older patients with long-term conditions. The baseline cross-sectional data from a longitudinal cohort study were analysed. Older patients (n=3378 aged 65 years and over) with a long-term condition registered in general practices were included in the study. The main outcome was patient-reported safety incidents including availability and appropriateness of medical tests and prescription of wrong types or doses of medication. Binary univariate and multivariate logistic regression analyses were undertaken to examine factors associated with patient-reported safety incidents. Safety incidents were reported by 11% of the patients. Four factors were significantly associated with patient-reported safety incidents in multivariate analyses. The experience of multiple long-term conditions (OR=1.09, 95% CI 1.05 to 1.13), a probable diagnosis of depression (OR=1.36, 95% CI 1.06 to 1.74) and greater relational continuity of care (OR=1.28, 95% CI 1.08 to 1.52) were associated with increased odds for patient-reported safety incidents. Perceived greater support and involvement in self-management was associated with lower odds for patient-reported safety incidents (OR=0.95, 95% CI 0.93 to 0.97). We found that older patients with multimorbidity and depression are more likely to report experiences of patient safety incidents. Improving perceived support and involvement of patients in their care may help prevent patient-reported safety incidents. © Article author(s) (or their employer(s) unless otherwise stated in the text of the article) 2017. All rights reserved. No commercial use is permitted unless otherwise expressly granted.

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

International Nuclear Information System (INIS)

Oedewald, Pia; Gotcheva, Nadezhda

2015-01-01

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

The influence of situation awareness training on nurses' confidence about patient safety skills: A prospective cohort study.

Science.gov (United States)

Stomski, Norman; Gluyas, Heather; Andrus, Prue; Williams, Anne; Hopkins, Martin; Walters, Jennifer; Sandy, Martinique; Morrison, Paul

2018-04-01

Several studies report that patient safety skills, especially non-technical skills, receive scant attention in nursing curricula. Hence, there is a compelling reason to incorporate material that enhances non-technical skills, such as situation awareness, in nursing curricula in order to assist in the reduction of healthcare related adverse events. The objectives of this study were to: 1) understand final year nursing students' confidence in their patient safety skills; and 2) examine the impact of situation awareness training on final year nursing students' confidence in their patient safety skills. Participants were enrolled from a convenience sample comprising final year nursing students at a Western Australia university. Self-reported confidence in patient safety skills was assessed with the Health Professional in Patient Safety Survey before and after the delivery of a situation awareness educational intervention. Pre/post educational intervention differences were examined by repeated measures ANOVA. No significant differences in confidence about patient safety skills were identified within settings (class/clinical). However, confidence in patient safety skills significantly decreased between settings i.e. nursing students lost confidence after clinical placements. The educational intervention delivered in this study did not seem to improve confidence in patient safety skills, but substantial ceiling effects may have confounded the identification of such improvement. Further studies are required to establish whether the findings of this study can be generalised to other university nursing cohorts. Copyright © 2018 Elsevier Ltd. All rights reserved.

Safety-in-numbers

DEFF Research Database (Denmark)

Elvik, Rune; Bjørnskau, Torkel

2017-01-01

Highlights •26 studies of the safety-in-numbers effect are reviewed. •The existence of a safety-in-numbers effect is confirmed. •Results are consistent. •Causes of the safety-in-numbers effect are incompletely known....

Studies and research relatives to the safety of the Super-Phenix project

International Nuclear Information System (INIS)

Anselin, F.; Penet, F.

1978-01-01

The analysis of safety reports concerning the Creys Malville power station (Superphenix) must be based on technical data supplied by the NERSA, responsible for the plant, and on results of research and development programme carried out in various establishments and at the CEA in particular. By virtue of the procedure laid down for the safety analysis, i.e. analysis by the barrier method, verification of reactor shut down rules at power, permanence of cooling, confinement of dangerous products in the event of hypothetical failure of the above two functions safety R and D programmes have a double aspect: accident prevention on the one hand and study of the development of accident, even the most hypothetical on the other. In the accident prevention field the studies deal with the resistance of barriers under normal and accidental working conditions, inspection systems and reactor safety functions allowing abnormal situations to be detected and the reactor shut down; whence the special emphasis placed on emergency shut-down and cooling systems. In the accident field the R and D activities cover a wide range of studies on phenomena liable to arise, independently of their probability of occurence during the lifetime of the reactor; heating in the mass or boiling of sodium, fuel, meeting, movements of fused materials, fuel-sodium thermal interaction, core deformation, resistance of confinement recovery of molten fuel, post-accident cooling, transfer of radioactivity and contamination outside the reactor, radiological consequences and means of confinement of dangerous products [fr

Application of patient safety indicators internationally: a pilot study among seven countries

OpenAIRE

Drösler, Saskia E.; Klazinga, Niek S.; Romano, Patrick S.; Tancredi, Daniel J.; Gogorcena Aoiz, Maria A.; Hewitt, Moira C.; Scobie, Sarah; Soop, Michael; Wen, Eugene; Quan, Hude; Ghali, William A.; Mattke, Soeren; Kelley, Edward

2017-01-01

Objective To explore the potential for international comparison of patient safety as part of the Health Care Quality Indicators project of the Organization for Economic Co-operation and Development (OECD) by evaluating patient safety indicators originally published by the US Agency for Healthcare Research and Quality (AHRQ). Design A retrospective cross-sectional study. Setting Acute care hospitals in the USA, UK, Sweden, Spain, Germany, Canada and Australia in 2004 and 2005/2006. Data source...

Assessing the validity of road safety evaluation studies by analysing causal chains.

Science.gov (United States)

Elvik, Rune

2003-09-01

This paper discusses how the validity of road safety evaluation studies can be assessed by analysing causal chains. A causal chain denotes the path through which a road safety measure influences the number of accidents. Two cases are examined. One involves chemical de-icing of roads (salting). The intended causal chain of this measure is: spread of salt --> removal of snow and ice from the road surface --> improved friction --> shorter stopping distance --> fewer accidents. A Norwegian study that evaluated the effects of salting on accident rate provides information that describes this causal chain. This information indicates that the study overestimated the effect of salting on accident rate, and suggests that this estimate is influenced by confounding variables the study did not control for. The other case involves a traffic club for children. The intended causal chain in this study was: join the club --> improve knowledge --> improve behaviour --> reduce accident rate. In this case, results are rather messy, which suggests that the observed difference in accident rate between members and non-members of the traffic club is not primarily attributable to membership in the club. The two cases show that by analysing causal chains, one may uncover confounding factors that were not adequately controlled in a study. Lack of control for confounding factors remains the most serious threat to the validity of road safety evaluation studies.

RAMONA-4B development for SBWR safety studies