Hydrogen Technologies Safety Guide

Energy Technology Data Exchange (ETDEWEB)

Rivkin, C. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Burgess, R. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Buttner, W. [National Renewable Energy Lab. (NREL), Golden, CO (United States)

2015-01-01

The purpose of this guide is to provide basic background information on hydrogen technologies. It is intended to provide project developers, code officials, and other interested parties the background information to be able to put hydrogen safety in context. For example, code officials reviewing permit applications for hydrogen projects will get an understanding of the industrial history of hydrogen, basic safety concerns, and safety requirements.

Instrumentation and control systems important to safety in nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

This Safety Guide was prepared under the IAEA programme for establishing safety standards for nuclear power plants. It supplements Safety Standards Series No. NS-R-1: Safety of Nuclear Power Plants: Design (the Requirements for Design), which establishes the design requirements for ensuring the safety of nuclear power plants. This Safety Guide describes how the requirements should be met for instrumentation and control (I and C) systems important to safety. This publication is a revision and combination of two previous Safety Guides: Safety Series Nos 50-SG-D3 and 50-SG-D8, which are superseded by this new Safety Guide. The revision takes account of developments in I and C systems important to safety since the earlier Safety Guides were published in 1980 and 1984, respectively. The objective of this Safety Guide is to provide guidance on the design of I and C systems important to safety in nuclear power plants, including all I and C components, from the sensors allocated to the mechanical systems to the actuated equipment, operator interfaces and auxiliary equipment. This Safety Guide deals mainly with design requirements for those I and C systems that are important to safety. It expands on paragraphs of Ref in the area of I and C systems important to safety. This publication is intended for use primarily by designers of nuclear power plants and also by owners and/or operators and regulators of nuclear power plants. This Safety Guide provides general guidance on I and C systems important to safety which is broadly applicable to many nuclear power plants. More detailed requirements and limitations for safe operation specific to a particular plant type should be established as part of the design process. The present guidance is focused on the design principles for systems important to safety that warrant particular attention, and should be applied to both the design of new I and C systems and the modernization of existing systems. Guidance is provided on how design

Safety assessment and verification for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2004-01-01

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

Safety assessment and verification for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

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

Periodic safety analyses; Les essais periodiques

Energy Technology Data Exchange (ETDEWEB)

Gouffon, A; Zermizoglou, R

1990-12-01

The IAEA Safety Guide 50-SG-S8 devoted to 'Safety Aspects of Foundations of Nuclear Power Plants' indicates that operator of a NPP should establish a program for inspection of safe operation during construction, start-up and service life of the plant for obtaining data needed for estimating the life time of structures and components. At the same time the program should ensure that the safety margins are appropriate. Periodic safety analysis are an important part of the safety inspection program. Periodic safety reports is a method for testing the whole system or a part of the safety system following the precise criteria. Periodic safety analyses are not meant for qualification of the plant components. Separate analyses are devoted to: start-up, qualification of components and materials, and aging. All these analyses are described in this presentation. The last chapter describes the experience obtained for PWR-900 and PWR-1300 units from 1986-1989.

Commissioning of research reactors. Safety guide

International Nuclear Information System (INIS)

2006-01-01

The objective of this Safety Guide is to provide recommendations on meeting the requirements for the commissioning of research reactors on the basis of international best practices. Specifically, it provides recommendations on fulfilling the requirements established in paras 6.44 and 7.42-7.50 of International Atomic Energy Agency, Safety of Research Reactors, IAEA Safety Standards Series No. NS-R-4, IAEA, Vienna (2005) and guidance and specific and consequential recommendations relating to the recommendations presented in paras 615-621 of International Atomic Energy Agency, Safety in the Utilization and Modification of Research Reactors, Safety Series No. 35-G2, IAEA, Vienna (1994) and paras 228-229 of International Atomic Energy Agency, Safety Assessment of Research Reactors and Preparation of the Safety Analysis Report, Safety Series No. 35-G1, IAEA, Vienna (1994). This Safety Guide is intended for use by all organizations involved in commissioning for a research reactor, including the operating organization, the regulatory body and other organizations involved in the research reactor project

Nuclear safety guide: TID--7016, Revision 2

International Nuclear Information System (INIS)

Thomas, J.T.

1978-01-01

The Nuclear Safety Guide was first issued in 1956 as classified AEC report LA-2063 and was reprinted the next year, unclassified, as TID-7016. Revision 1, published in 1961, extended the scope and refined the guiding information. Revision 2 of the Guide differs significantly from its predecessor in that the latter was intentionally conservative in its recommendations. Firmly based on experimental evidence of criticality, the original Guide and the first revision were considered to be of most value to organizations whose activities with fissionable materials were not extensive and, secondarily, that it would serve as a point of departure for members of established nuclear safety teams experienced in the field. The advance of calculational capability has permitted validated calculations to extend and substitute for experimental data. The broadened data base has enabled better interpolation, extension, and understanding of available information, especially in areas previously addressed by undefined but adequate factors of safety. The content has been thereby enriched in qualitative guidance. The information inherently contains, and the user can recapture, the quantitative guidance characteristic of the former Guides by employing appropriate safety factors

Safety design guides for fire protection for CANDU 9

International Nuclear Information System (INIS)

Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young; A. C. D. Wright

1996-03-01

This safety design guide establishes design requirements to ensure the radiological risk to the public due to fire is acceptable and operating personnel are adequately protected from the hazards of fires. This safety design guide also specifies the safety criteria for fire protection to be applied to mitigate fires and recommends the fire protection program to be established to initiate, coordinate and document the design activities associated with fire protection. The requirements for fire protection outlined in this safety design guide shall be satisfied in the design stage and the change status of the regulatory requirements, code and standards should be traced and incorporated into this safety design guide accordingly. 1 fig., (Author) .new

Deterministic Safety Analysis for Nuclear Power Plants. Specific Safety Guide (Russian Edition)

International Nuclear Information System (INIS)

2014-01-01

The objective of this Safety Guide is to provide harmonized guidance to designers, operators, regulators and providers of technical support on deterministic safety analysis for nuclear power plants. It provides information on the utilization of the results of such analysis for safety and reliability improvements. The Safety Guide addresses conservative, best estimate and uncertainty evaluation approaches to deterministic safety analysis and is applicable to current and future designs. Contents: 1. Introduction; 2. Grouping of initiating events and associated transients relating to plant states; 3. Deterministic safety analysis and acceptance criteria; 4. Conservative deterministic safety analysis; 5. Best estimate plus uncertainty analysis; 6. Verification and validation of computer codes; 7. Relation of deterministic safety analysis to engineering aspects of safety and probabilistic safety analysis; 8. Application of deterministic safety analysis; 9. Source term evaluation for operational states and accident conditions; References

Guide sur l'innovation dans les contextes non structurés | CRDI ...

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

14 nov. 2012 ... La croissance économique rapide enregistrée dans des pays en développement a accentué les inégalités de revenus, faisant ainsi ressortir la nécessité d'assurer un développement équitable. La notion d'innovation au service du développement inclusif offre à cet égard une piste de solution. Le guide ...

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

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-05-15

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

Meteorological events in site evaluation for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

This Safety Guide provides recommendations and guidance on conducting hazard assessments of extreme and rare meteorological phenomena. It is of interest to safety assessors and regulators involved in the licensing process as well as to designers of nuclear power plants. This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. It supplements the IAEA Safety Requirements publication on Site Evaluation for Nuclear Facilities which is to supersede the Code on the Safety of Nuclear Power Plants: Siting, Safety Series No. 50-C-S (Rev. 1), IAEA, Vienna (1988). The present Safety Guide supersedes two earlier Safety Guides: Safety Series No. 50-SG-S11A (1981) on Extreme Meteorological Events in Nuclear Power Plant Siting, Excluding Tropical Cyclones and Safety Series No. 50-SG-S11B (1984) on Design Basis Tropical Cyclone for Nuclear Power Plants. The purpose of this Safety Guide is to provide recommendations and guidance on conducting hazard assessments of extreme and rare meteorological phenomena. This Safety Guide provides interpretation of the Safety Requirements publication on Site Evaluation for Nuclear Facilities and guidance on how to fulfil these requirements. It is aimed at safety assessors or regulators involved in the licensing process as well as designers of nuclear power plants, and provides them with guidance on the methods and procedures for analyses that support the assessment of the hazards associated with extreme and rare meteorological events. This Safety Guide discusses the extreme values of meteorological variables and rare meteorological phenomena, as well as their rates of occurrence, according to the following definitions: (a) Extreme values of meteorological variables such as air temperature and wind speed characterize the meteorological or climatological environment. And (b) Rare meteorological phenomena

Ageing Management for Research Reactors. Specific Safety Guide

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-10-15

This Safety Guide was developed under the IAEA programme for safety standards for research reactors, which covers all the important areas of research reactor safety. It supplements and elaborates upon the safety requirements for ageing management of research reactors that are established in paras 6.68-6.70 and 7.109 of the IAEA Safety Requirements publication, Safety of Research Reactors. The safety of a research reactor requires that provisions be made in its design to facilitate ageing management. Throughout the lifetime of a research reactor, including its decommissioning, ageing management of its structures, systems and components (SSCs) important to safety is required, to ensure continued adequacy of the safety level, reliable operation of the reactor, and compliance with the operational limits and conditions. Managing the safety aspects of research reactor ageing requires implementation of an effective programme for the monitoring, prediction, and timely detection and mitigation of degradation of SSCs important to safety, and for maintaining their integrity and functional capability throughout their service lives. Ageing management is defined as engineering, operation, and maintenance strategy and actions to control within acceptable limits the ageing degradation of SSCs. Ageing management includes activities such as repair, refurbishment and replacement of SSCs, which are similar to other activities carried out at a research reactor in maintenance and testing or when a modification project takes place. However, it is important to recognize that effective management of ageing requires the use of a methodology that will detect and evaluate ageing degradation as a consequence of the service conditions, and involves the application of countermeasures for prevention and mitigation of ageing degradation. The objective of this Safety Guide is to provide recommendations on managing ageing of SSCs important to safety at research reactors on the basis of international

Ageing Management for Research Reactors. Specific Safety Guide

International Nuclear Information System (INIS)

2010-01-01

This Safety Guide was developed under the IAEA programme for safety standards for research reactors, which covers all the important areas of research reactor safety. It supplements and elaborates upon the safety requirements for ageing management of research reactors that are established in paras 6.68-6.70 and 7.109 of the IAEA Safety Requirements publication, Safety of Research Reactors. The safety of a research reactor requires that provisions be made in its design to facilitate ageing management. Throughout the lifetime of a research reactor, including its decommissioning, ageing management of its structures, systems and components (SSCs) important to safety is required, to ensure continued adequacy of the safety level, reliable operation of the reactor, and compliance with the operational limits and conditions. Managing the safety aspects of research reactor ageing requires implementation of an effective programme for the monitoring, prediction, and timely detection and mitigation of degradation of SSCs important to safety, and for maintaining their integrity and functional capability throughout their service lives. Ageing management is defined as engineering, operation, and maintenance strategy and actions to control within acceptable limits the ageing degradation of SSCs. Ageing management includes activities such as repair, refurbishment and replacement of SSCs, which are similar to other activities carried out at a research reactor in maintenance and testing or when a modification project takes place. However, it is important to recognize that effective management of ageing requires the use of a methodology that will detect and evaluate ageing degradation as a consequence of the service conditions, and involves the application of countermeasures for prevention and mitigation of ageing degradation. The objective of this Safety Guide is to provide recommendations on managing ageing of SSCs important to safety at research reactors on the basis of international

Regulatory control of radiation sources. Safety guide

International Nuclear Information System (INIS)

2004-01-01

The basic requirements for the protection of persons against exposure to ionizing radiation and for the safety of radiation sources were established in the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (the Basic Safety Standards), jointly sponsored by the Food and Agriculture Organization of the United Nations (FAO), the International Atomic Energy Agency (IAEA), the International Labour Organization (ILO), the OECD Nuclear Energy Agency (OECD/ NEA), the Pan American Health Organization (PAHO) and the World Health Organization (WHO) (the Sponsoring Organizations). The application of the Basic Safety Standards is based on the presumption that national infrastructures are in place to enable governments to discharge their responsibilities for radiation protection and safety. Requirements relating to the legal and governmental infrastructure for the safety of nuclear facilities and sources of ionizing radiation, radiation protection, the safe management of radioactive waste and the safe transport of radioactive material are established in the Safety Requirements on Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety, Safety Standards Series No. GS-R-1. This Safety Guide, which is jointly sponsored by the FAO, the IAEA, the International Labour Office, the PAHO and the WHO, gives detailed guidance on the key elements for the organization and operation of a national regulatory infrastructure for radiation safety, with particular reference to the functions of the national regulatory body that are necessary to ensure the implementation of the Basic Safety Standards. The Safety Guide is based technically on material first published in IAEA-TECDOC-10671, which was jointly sponsored by the FAO, the IAEA, the OECD/NEA, the PAHO and the WHO. The requirements established in GS-R-1 have been taken into account. The Safety Guide is oriented towards national

Radiation Safety in Industrial Radiography. Specific Safety Guide

International Nuclear Information System (INIS)

2011-01-01

This Safety Guide provides recommendations for ensuring radiation safety in industrial radiography used in non-destructive testing. This includes industrial radiography work that utilizes X ray and gamma sources, both in shielded facilities that have effective engineering controls and in outside shielded facilities using mobile sources. Contents: 1. Introduction; 2. Duties and responsibilities; 3. Safety assessment; 4. Radiation protection programme; 5. Training and qualification; 6. Individual monitoring of workers; 7. Workplace monitoring; 8. Control of radioactive sources; 9. Safety of industrial radiography sources and exposure devices; 10. Radiography in shielded enclosures; 11. Site radiography; 12. Transport of radioactive sources; 13. Emergency preparedness and response; Appendix: IAEA categorization of radioactive sources; Annex I: Example safety assessment; Annex II: Overview of industrial radiography sources and equipment; Annex III: Examples of accidents in industrial radiography.

Regulatory Control of Radiation Sources. Safety Guide

International Nuclear Information System (INIS)

2009-01-01

This Safety Guide is intended to assist States in implementing the requirements established in Safety Standards Series No. GS-R-1, Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety, for a national regulatory infrastructure to regulate any practice involving radiation sources in medicine, industry, research, agriculture and education. The Safety Guide provides advice on the legislative basis for establishing regulatory bodies, including the effective independence of the regulatory body. It also provides guidance on implementing the functions and activities of regulatory bodies: the development of regulations and guides on radiation safety; implementation of a system for notification and authorization; carrying out regulatory inspections; taking necessary enforcement actions; and investigating accidents and circumstances potentially giving rise to accidents. The various aspects relating to the regulatory control of consumer products are explained, including justification, optimization of exposure, safety assessment and authorization. Guidance is also provided on the organization and staffing of regulatory bodies. Contents: 1. Introduction; 2. Legal framework for a regulatory infrastructure; 3. Principal functions and activities of the regulatory body; 4. Regulatory control of the supply of consumer products; 5. Functions of the regulatory body shared with other governmental agencies; 6. Organization and staffing of the regulatory body; 7. Documentation of the functions and activities of the regulatory body; 8. Support services; 9. Quality management for the regulatory system.

Safety guide on fire protection in nuclear power plants

International Nuclear Information System (INIS)

1976-01-01

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

Preclosure Safety Analysis Guide

International Nuclear Information System (INIS)

D.D. Orvis

2003-01-01

A preclosure safety analysis (PSA) is a required element of the License Application (LA) for the high- level radioactive waste repository at Yucca Mountain. This guide provides analysts and other Yucca Mountain Repository Project (the Project) personnel with standardized methods for developing and documenting the PSA. The definition of the PSA is provided in 10 CFR 63.2, while more specific requirements for the PSA are provided in 10 CFR 63.112, as described in Sections 1.2 and 2. The PSA requirements described in 10 CFR Part 63 were developed as risk-informed performance-based regulations. These requirements must be met for the LA. The PSA addresses the safety of the Geologic Repository Operations Area (GROA) for the preclosure period (the time up to permanent closure) in accordance with the radiological performance objectives of 10 CFR 63.111. Performance objectives for the repository after permanent closure (described in 10 CFR 63.113) are not mentioned in the requirements for the PSA and they are not considered in this guide. The LA will be comprised of two phases: the LA for construction authorization (CA) and the LA amendment to receive and possess (R and P) high-level radioactive waste (HLW). PSA methods must support the safety analyses that will be based on the differing degrees of design detail in the two phases. The methods described herein combine elements of probabilistic risk assessment (PRA) and deterministic analyses that comprise a risk-informed performance-based safety analysis. This revision to the PSA guide was prepared for the following objectives: (1) To correct factual and typographical errors. (2) To provide additional material suggested from reviews by the Project, the U.S. Department of Energy (DOE), and U.S. Nuclear Regulatory Commission (NRC) Staffs. (3) To update material in accordance with approaches and/or strategies adopted by the Project. In addition, a principal objective for the planned revision was to ensure that the methods and

Development of Safety Review Guide for the Periodic Safety Review of Reactor Vessel Internals

International Nuclear Information System (INIS)

Park, Jeongsoon; Ko, Hanok; Kim, Seonjae; Jhung, Myungjo

2013-01-01

Aging management of the reactor vessel internals (RVIs) is one of the important issues for long-term operation of nuclear power plants (NPPs). Safety review on the assessment and management of the RVI aging is conducted through the process of a periodic safety review (PSR). The regulatory body should check that reactor facilities sustain safety functions in light of degradation due to aging and that the operator of a nuclear power reactor establishes and implements management program to deal with degradation due to aging in order to guarantee the safety functions and the safety margin as a result of PSR. KINS(Korea Institute of Nuclear Safety) has utilized safety review guides (SRG) which provide guidance to KINS staffs in performing safety reviews in order to assure the quality and uniformity of staff safety reviews. The KINS SRGs for the continued operation of pressurized water reactors (PWRs) published in 2006 contain areas of review regarding aging management of RVIs in chapter 2 (III.2.15, Appendix 2.0.1). However unlike the SRGs for the continued operation, KINS has not officially published the SRGs for the PSR of PWRs, but published them as a form of the research report. In addition to that, the report provides almost same review procedures for aging assessment and management of RVIs with the ones provided in the SRGs for the continued operation, it cannot provide review guidance specific to PSRs. Therefore, a PSR safety review guide should be developed for RVIs in PWRs. In this study, a draft PSR safety review guide for reactor vessel internals in PWRs is developed and provided. In this paper, a draft PSR safety review guide for reactor vessel internals (PSR SRG-RVIs) in PWRs is introduced and main contents of the draft are provided. However, since the PSR safety review guides for areas other than RVIs in the pressurized water reactors (PWRs) are expected to be developed in the near future, the draft PSR SRG-RVIs should be revisited to be compatible with

Safety design guide for safety related systems for CANDU 9

International Nuclear Information System (INIS)

Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young; A. C. D. Wright

1996-03-01

In general, two types of safety related systems and structures exist in the nuclear plant; The one is a systems and structures which perform safety functions during the normal operation of the plant, and the other is a systems and structures which perform safety functions to mitigate events caused by failure of the normally operating systems or by naturally occurring phenomena. In this safety design guide, these systems are identified in detail, and the major events for which the safety functions are required and the major safety requirements are identified in the list. As the probabilistic safety assessments are completed during the course of the project, additions or deletions to the list may be justified. 3 tabs. (Author) .new

Safety design guide for safety related systems for CANDU 9

Energy Technology Data Exchange (ETDEWEB)

Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young [Korea Atomic Energy Research Institute, Daeduk (Korea, Republic of); Wright, A.C.D. [Atomic Energy of Canada Ltd., Toronto (Canada)

1996-03-01

In general, two types of safety related systems and structures exist in the nuclear plant; The one is a systems and structures which perform safety functions during the normal operation of the plant, and the other is a systems and structures which perform safety functions to mitigate events caused by failure of the normally operating systems or by naturally occurring phenomena. In this safety design guide, these systems are identified in detail, and the major events for which the safety functions are required and the major safety requirements are identified in the list. As the probabilistic safety assessments are completed during the course of the project, additions or deletions to the list may be justified. 3 tabs. (Author) .new.

Laboratory Safety Guide for Arkansas K-12 Schools.

Science.gov (United States)

Arkansas State Dept. of Education, Little Rock.

This document presents laboratory safety rules for Arkansas K-12 schools which were developed by the Arkansas Science Teachers Association (ASTA) and the Arkansas Department of Education (ADE). Contents include: (1) "Laboratory Safety Guide for Arkansas K-12 Schools"; (2) "Safety Considerations"; (3) "Safety Standards for Science Laboratories";…

The operating organization for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2001-01-01

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

The operating organization for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

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

The operating organization for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2004-01-01

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

Modifications to nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2004-01-01

This Safety Guide was prepared under the IAEA's programme for safety standards for nuclear power plants. It supplements Section 7 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation, which establishes the safety requirements for the modification of nuclear power plants. Reasons for carrying out modifications to nuclear power plants may include: (1) maintaining or strengthening existing safety provisions and thus maintaining consistency with or improving on the current design. (2) recovering from plant faults. (3) improving the thermal performance or increasing the power rating of the plant. (4) increasing the maintainability of the plant, reducing the radiation exposure of personnel or reducing the costs of plant maintenance. And (5) extending the design life of the plant. Most modifications, made on the basis of operating experience, are intended to improve on the design or to improve operational performance and flexibility. Some are rendered necessary by new regulatory requirements, ageing of the plant or obsolescence of equipment. However, the benefits of regularly updating the plant design can be jeopardized if modifications are not kept under rigorous control throughout the lifetime of the plant. The need to reduce costs and improve efficiency, in combination with changes to the structure of the electricity generation sector of the economy in many countries, has led many companies to make changes in the structure of the operating organization for nuclear power plants. Whatever the reason for such organizational changes, consideration should be given to the effects of those changes with the aim of ensuring that they would have no impacts that would compromise the safety of the plant. The objective of this Safety Guide is to provide guidance and recommendations on controlling activities relating to modifications at nuclear power plants in order to reduce risk and to ensure that the configuration of the plant is at all times under

Modifications to nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2007-01-01

This Safety Guide was prepared under the IAEA's programme for safety standards for nuclear power plants. It supplements Section 7 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation, which establishes the safety requirements for the modification of nuclear power plants. Reasons for carrying out modifications to nuclear power plants may include: (1) maintaining or strengthening existing safety provisions and thus maintaining consistency with or improving on the current design. (2) recovering from plant faults. (3) improving the thermal performance or increasing the power rating of the plant. (4) increasing the maintainability of the plant, reducing the radiation exposure of personnel or reducing the costs of plant maintenance. And (5) extending the design life of the plant. Most modifications, made on the basis of operating experience, are intended to improve on the design or to improve operational performance and flexibility. Some are rendered necessary by new regulatory requirements, ageing of the plant or obsolescence of equipment. However, the benefits of regularly updating the plant design can be jeopardized if modifications are not kept under rigorous control throughout the lifetime of the plant. The need to reduce costs and improve efficiency, in combination with changes to the structure of the electricity generation sector of the economy in many countries, has led many companies to make changes in the structure of the operating organization for nuclear power plants. Whatever the reason for such organizational changes, consideration should be given to the effects of those changes with the aim of ensuring that they would have no impacts that would compromise the safety of the plant. The objective of this Safety Guide is to provide guidance and recommendations on controlling activities relating to modifications at nuclear power plants in order to reduce risk and to ensure that the configuration of the plant is at all times under

The safety evaluation guide for laboratories and plants a tool for enhancing safety

International Nuclear Information System (INIS)

Lhomme, Veronique; Daubard, Jean-Paul

2013-01-01

The Institute for Radioprotection and Nuclear Safety (IRSN) acts as technical support for the French government Authorities competent in nuclear safety and radiation protection for civil and defence activities. In this frame, the Institute's performs safety assessments of the safety cases submitted by operators to these Authorities for each stage in the life cycle of a nuclear facility, including dismantling operations, which is subjected to a licensing procedure. In the fuel cycle field, this concerns a large variety of facilities. Very often, depending on facilities and on safety cases, safety assessment to be performed is multidisciplinary and involves the supervisor in charge of the facility and several safety experts, particularly to cover the whole set of risks (criticality, exposure to radiation, fire, handling, containment, human and organisational factors...) encountered during facility's operations. Taking these into account, and in order to formalize the assessment process of the fuel cycle facilities, laboratories, irradiators, particle accelerators, under-decommissioning reactors and radioactive waste management, the 'Plants, Laboratories, Transports and Waste Safety' Division of IRSN has developed an internal guide, as a tool: - To present the methodological framework, and possible specificities, for the assessment according to the 'Defence in Depth Concept' (Part 1); - To provide key questions associated to the necessary contradictory technical review of the safety cases (Part 2); - To capitalise on experience on the basis of technical examples (coming from incident reports, previous safety assessments...) demonstrating the questioning (Part 3). The guide is divided in chapters, each dedicated to a type of risk (dissemination of radioactive material, external or internal exposure from ionising radiation, criticality, radiolysis mechanisms, handling operations, earthquake, human or organisational factors...) or to a type

Decommissioning of nuclear fuel cycle facilities. Safety guide

International Nuclear Information System (INIS)

2001-01-01

The objective of this Safety Guide is to provide guidance to regulatory bodies and operating organizations on planning and provision for the safe management of the decommissioning of non-reactor nuclear fuel cycle facilities. While the basic safety considerations for the decommissioning of nuclear fuel cycle facilities are similar to those for nuclear power plants, there are important differences, notably in the design and operating parameters for the facilities, the type of radioactive material and the support systems available. It is the objective of this Safety Guide to provide guidance for the shutdown and eventual decommissioning of such facilities, their individual characteristics being taken into account

Safety design guides for seismic requirements for CANDU 9

International Nuclear Information System (INIS)

Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young; A. C. D. Wright

1996-03-01

This safety design guide for seismic requirements for CANDU 9 describes the seismic design philosophy, defines the applicable earthquakes and identifies the structures and systems requiring seismic qualification to ensure that the essential safety function can be adequately satisfied following earthquake. The detailed requirements for structures, systems and components which must be seismically qualified are specified in the Appendix. The change status of the regulatory requirements, code and standards should be traced and this safety design guide shall be updated accordingly. 1 fig., (Author) .new

Guide for understanding and evaluation of safety culture

International Nuclear Information System (INIS)

2008-01-01

This report was the guide of understanding and evaluation of safety culture. Operator's activities for enhancement of safety culture in nuclear installations became an object of safety regulation in the management system. Evaluation of operator's activities (including top management's involvement) to prevent degradation of safety culture and organization climate in daily works needed understanding of safety culture and diversity of operator's activities. This guide was prepared to check indications of degradation of safety culture and organization climate in operator's activities in daily works and encourage operator's activities to enhance safety culture improvement and good practice. Comprehensive evaluation of operator's activities to prevent degradation of safety culture and organization climate would be performed from the standpoints of 14 safety culture elements such as top management commitment, clear plan and implementation of upper manager, measures to avoid wrong decision making, questioning attitude, reporting culture, good communications, accountability and openness, compliance, learning system, activities to prevent accidents or incidents beforehand, self-assessment or third party evaluation, work management, change management and attitudes/motivation. Element-wise examples and targets for evaluation were attached with evaluation check tables. (T. Tanaka)

Radiation Safety of Gamma, Electron and X Ray Irradiation Facilities. Specific Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2015-01-01

The objective of this Safety Guide is to provide recommendations on how to meet the requirements of the BSS with regard to irradiation facilities. This Safety Guide provides specific, practical recommendations on the safe design and operation of gamma, electron and X ray irradiators for use by operating organizations and the designers of these facilities, and by regulatory bodies. SCOPE. The facilities considered in this publication include five types of irradiator, whether operated on a commercial basis or for research and development purposes. This publication is concerned with radiation safety issues and not with the uses of irradiators, nor does it cover the irradiation of product or its quality management. The five types of irradiator are: - Panoramic dry source storage irradiators; - Underwater irradiators, in which both the source and the product being irradiated are under water; - Panoramic wet source storage irradiators; - Electron beam irradiation facilities, in which irradiation is performed in an area that is potentially accessible to personnel, but that is kept inaccessible during the irradiation process; - X ray irradiation facilities, in which irradiation is performed in an area that is potentially accessible to personnel, but that is kept inaccessible during the irradiation process. Consideration of non-radiation-related risks and of the benefits resulting from the operation of irradiators is outside the scope of this Safety Guide. The practices of radiotherapy and radiography are also outside the scope of this Safety Guide. Category I gamma irradiators (i.e. 'self-shielded' irradiators) are outside the scope of this Safety Guide

Predisposal management of high level radioactive waste. Safety guide

International Nuclear Information System (INIS)

2005-01-01

Radioactive waste is generated in the generation of electricity in nuclear power plants and in the use of radioactive material in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized. The principles and requirements that govern the safety of the management of radioactive waste are presented in 'The Principles of Radioactive Waste Management', 'Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety' and 'Predisposal Management of Radioactive Waste, Including Decommissioning'. The objective of this Safety Guide is to provide regulatory bodies and the operators that generate and manage radioactive waste with recommendations on how to meet the principles and requirements established in Refs for the predisposal management of HLW. This Safety Guide applies to the predisposal management of HLW. For liquid HLW arising from the reprocessing of spent fuel the recommendations of this Safety Guide apply from when liquid waste from the first extraction process is collected for storage and subsequent processing. Recommendations and guidance on the storage of spent fuel, whether or not declared as waste, subsequent to its removal from the storage facility of a reactor are provided in Refs. For spent fuel declared as waste this Safety Guide applies to all activities subsequent to its removal from the storage facility of a reactor and prior to its disposal. Requirements pertaining to the transport of spent fuel, whether or not declared as waste, and of all forms of HLW are established. This Safety Guide provides recommendations on the safety aspects of managing HLW, including the planning, design, construction, commissioning, operation and decommissioning of equipment or facilities for the predisposal management of HLW. It addresses the following elements: (a) The characterization and processing (i.e. pretreatment

Safety inspection guide, Mod III (a systematic approach to conducting a safety inspection)

International Nuclear Information System (INIS)

Davidson, J.E.

1977-06-01

This guide was developed as a comprehensive/systematic approach to the problem of performing a safety inspection. Five basic sections (categories) are considered in the guide: physical work place; machines/mechanical equipment; hazardous materials/processes/environments; energy sources; and management hazard . control factors. The basic concept is that one starts evaluating hazard potentials from the physical work place and continues considering other elements as they are added to the physical work place. This approach provides a better understanding of the interfaces of each section to the entire group. The guide is supported by an Area Safety Inspection Result form to record defects or conditions found, the evaluation (best estimate) of the urgency or priority for correcting deficiencies or areas of noncompliance, and the status of corrective action. Additionally, the guide serves as an educational tool in accident prevention for supervisors and employees

Operational limits and conditions and operating procedures for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

This Safety Guide was prepared as part of the Agency's programme for establishing safety standards relating to nuclear power plants. The present Safety Guide supersedes the IAEA Safety Guide on Operational Limits and Conditions for Nuclear Power Plants which was issued in 1979 as Safety Series No. 50-SG-O3. For a nuclear power plant to be operated in a safe manner, the provisions made in the final design and subsequent modifications shall be reflected in limitations on plant operating parameters and in the requirements on plant equipment and personnel. Under the responsibility of the operating organization, these shall be developed during the design safety evaluation as a set of operational limits and conditions (OLCs). A major contribution to compliance with the OLCs is made by the development and utilization of operating procedures (OPs) that are consistent with and fully implement the OLCs. The requirements for the OLCs and OPs are established in Section 5 of the IAEA Safety Requirements publication Safety of Nuclear Power Plants: Operation, which this Safety Guide supplements. The purpose of this Safety Guide is to provide guidance on the development, content and implementation of OLCs and OPs. The Safety Guide is directed at both regulators and owners/operators. This Safety Guide covers the concept of OLCs, their content as applicable to land based stationary power plants with thermal neutron reactors, and the responsibilities of the operating organization regarding their establishment, modification, compliance and documentation. The OPs to support the implementation of the OLCs and to ensure their observance are also within the scope of this Safety Guide. The particular aspects of the procedures for maintenance, surveillance, in-service inspection and other safety related activities in connection with the safe operation of nuclear power plants are outside the scope of this Safety Guide but can be found in other IAEA Safety Guides. Section 2 indicates the

Operational limits and conditions and operating procedures for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2000-01-01

This Safety Guide was prepared as part of the Agency's programme for establishing safety standards relating to nuclear power plants. The present Safety Guide supersedes the IAEA Safety Guide on Operational Limits and Conditions for Nuclear Power Plants which was issued in 1979 as Safety Series No. 50-SG-O3. For a nuclear power plant to be operated in a safe manner, the provisions made in the final design and subsequent modifications shall be reflected in limitations on plant operating parameters and in the requirements on plant equipment and personnel. Under the responsibility of the operating organization, these shall be developed during the design safety evaluation as a set of operational limits and conditions (OLCs). A major contribution to compliance with the OLCs is made by the development and utilization of operating procedures (OPs) that are consistent with and fully implement the OLCs. The requirements for the OLCs and OPs are established in Section 5 of the IAEA Safety Requirements publication Safety of Nuclear Power Plants: Operation, which this Safety Guide supplements. The purpose of this Safety Guide is to provide guidance on the development, content and implementation of OLCs and OPs. The Safety Guide is directed at both regulators and owners/operators. This Safety Guide covers the concept of OLCs, their content as applicable to land based stationary power plants with thermal neutron reactors, and the responsibilities of the operating organization regarding their establishment, modification, compliance and documentation. The OPs to support the implementation of the OLCs and to ensure their observance are also within the scope of this Safety Guide. The particular aspects of the procedures for maintenance, surveillance, in-service inspection and other safety related activities in connection with the safe operation of nuclear power plants are outside the scope of this Safety Guide but can be found in other IAEA Safety Guides. Section 2 indicates the

Predisposal management of low and intermediate level radioactive waste. Safety guide

International Nuclear Information System (INIS)

2003-01-01

Radioactive waste is generated in the generation of electricity in nuclear power reactors and in the use of radioactive material in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized. The principles and requirements that govern the safety of the management of radioactive waste are presented in 'The Principles of Radioactive Waste Management', 'Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety' and 'Predisposal Management of Radioactive Waste, Including Decommissioning'. The objective of this Safety Guide is to provide regulatory bodies and the operators that generate and manage radioactive waste with recommendations on how to meet the principles and requirements established in Refs for the predisposal management of LLW. This Safety Guide deals with the safety issues associated with the predisposal management of LLW from nuclear fuel cycle facilities, large research and development installations and radioisotope production facilities. This includes all steps and activities in the management of waste, from its initial generation to its final acceptance at a waste disposal facility or the removal of regulatory control. The predisposal management of radioactive waste includes decommissioning. The term 'decommissioning' encompasses both the process of decommissioning a facility and the management of the waste that results (prior to its disposal). Recommendations on the process of decommissioning are provided in Refs. Recommendations on the management of the waste resulting from decommissioning are included in this Safety Guide. Although the mining and milling of uranium and thorium ores is part of the nuclear fuel cycle, the management of the operational waste (e.g. waste rock, tailings and effluent treatment waste) from these activities is not within the scope of this Safety Guide. The LLW that is

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

Software for computer based systems important to safety in nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2004-01-01

Computer based systems are of increasing importance to safety in nuclear power plants as their use in both new and older plants is rapidly increasing. They are used both in safety related applications, such as some functions of the process control and monitoring systems, as well as in safety critical applications, such as reactor protection or actuation of safety features. The dependability of computer based systems important to safety is therefore of prime interest and should be ensured. With current technology, it is possible in principle to develop computer based instrumentation and control systems for systems important to safety that have the potential for improving the level of safety and reliability with sufficient dependability. However, their dependability can be predicted and demonstrated only if a systematic, fully documented and reviewable engineering process is followed. Although a number of national and international standards dealing with quality assurance for computer based systems important to safety have been or are being prepared, internationally agreed criteria for demonstrating the safety of such systems are not generally available. It is recognized that there may be other ways of providing the necessary safety demonstration than those recommended here. The basic requirements for the design of safety systems for nuclear power plants are provided in the Requirements for Design issued in the IAEA Safety Standards Series.The IAEA has issued a Technical Report to assist Member States in ensuring that computer based systems important to safety in nuclear power plants are safe and properly licensed. The report provides information on current software engineering practices and, together with relevant standards, forms a technical basis for this Safety Guide. The objective of this Safety Guide is to provide guidance on the collection of evidence and preparation of documentation to be used in the safety demonstration for the software for computer based

Software for computer based systems important to safety in nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

Computer based systems are of increasing importance to safety in nuclear power plants as their use in both new and older plants is rapidly increasing. They are used both in safety related applications, such as some functions of the process control and monitoring systems, as well as in safety critical applications, such as reactor protection or actuation of safety features. The dependability of computer based systems important to safety is therefore of prime interest and should be ensured. With current technology, it is possible in principle to develop computer based instrumentation and control systems for systems important to safety that have the potential for improving the level of safety and reliability with sufficient dependability. However, their dependability can be predicted and demonstrated only if a systematic, fully documented and reviewable engineering process is followed. Although a number of national and international standards dealing with quality assurance for computer based systems important to safety have been or are being prepared, internationally agreed criteria for demonstrating the safety of such systems are not generally available. It is recognized that there may be other ways of providing the necessary safety demonstration than those recommended here. The basic requirements for the design of safety systems for nuclear power plants are provided in the Requirements for Design issued in the IAEA Safety Standards Series.The IAEA has issued a Technical Report to assist Member States in ensuring that computer based systems important to safety in nuclear power plants are safe and properly licensed. The report provides information on current software engineering practices and, together with relevant standards, forms a technical basis for this Safety Guide. The objective of this Safety Guide is to provide guidance on the collection of evidence and preparation of documentation to be used in the safety demonstration for the software for computer based

Software for computer based systems important to safety in nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2000-01-01

Computer based systems are of increasing importance to safety in nuclear power plants as their use in both new and older plants is rapidly increasing. They are used both in safety related applications, such as some functions of the process control and monitoring systems, as well as in safety critical applications, such as reactor protection or actuation of safety features. The dependability of computer based systems important to safety is therefore of prime interest and should be ensured. With current technology, it is possible in principle to develop computer based instrumentation and control systems for systems important to safety that have the potential for improving the level of safety and reliability with sufficient dependability. However, their dependability can be predicted and demonstrated only if a systematic, fully documented and reviewable engineering process is followed. Although a number of national and international standards dealing with quality assurance for computer based systems important to safety have been or are being prepared, internationally agreed criteria for demonstrating the safety of such systems are not generally available. It is recognized that there may be other ways of providing the necessary safety demonstration than those recommended here. The basic requirements for the design of safety systems for nuclear power plants are provided in the Requirements for Design issued in the IAEA Safety Standards Series.The IAEA has issued a Technical Report to assist Member States in ensuring that computer based systems important to safety in nuclear power plants are safe and properly licensed. The report provides information on current software engineering practices and, together with relevant standards, forms a technical basis for this Safety Guide. The objective of this Safety Guide is to provide guidance on the collection of evidence and preparation of documentation to be used in the safety demonstration for the software for computer based

Des Guides Joanne au Guide Vert Michelin : points, lignes, surfaces

Directory of Open Access Journals (Sweden)

Marie-Vic Ozouf-Marignier

2011-06-01

Full Text Available Cet article étudie la perception de l’espace dans les guides touristiques de la fin du XIXe siècle à nos jours. Il compare trois collections de guides français : les Guides Joanne, les Guides Bleus Hachette et les Guides Verts Michelin. Nous avons identifié trois moments majeurs. Dans une première période, le voyage en chemin de fer détermine une représentation linéaire de l’espace agrémentée de quelques coups d’œil à l’intérieur du paysage à l’endroit des stations. Dans une seconde période, le déplacement en voiture permet à une appréhension régionale de se développer. L’école française de géographie influence alors l’écriture des introductions de guide. Les rédacteurs introduisent de plus en plus de cartes dans ces ouvrages. L’unité régionale devient sensible, notamment du point de vue naturaliste. Toutefois, la recherche des curiosités, musées églises, châteaux et ruines se maintient également. De nos jours, l’autoroute, le train à grande vitesse et l’industrie touristique ont changé les pratiques et représentations de l’espace. Les touristes semblent apprécier le fait de collectionner les sites de visite et de faire des circuits à thème.This article deals with tourist perception of the space from the end of the nineteenth century to our days. It compares three collections of French tourist guides: Guides Joanne, blue guides Hachette and Guides Verts Michelin. Three main periods can be distinguished. First, railway travel determines linear representation of the landscape, with a few glances on the countryside at the stations. In a second period, the car mobility makes possible a surrounding vision of regions. French school of geography influences the prefaces of the guides. Editors introduce more and more maps inside the guides. Regional cohesion becomes perceptible, especially from a naturalistic point of view. Interesting sights, museums, churches, castles and ruins remain

Decommissioning of Medical, Industrial and Research Facilities. Safety Guide

International Nuclear Information System (INIS)

2010-01-01

Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of medical, industrial and research facilities where radioactive materials and sources are produced, received, used and stored. It is intended to provide guidance to national authorities and operating organizations, particularly to those in developing countries (as such facilities are predominant in these countries), for the planning and safe management of the decommissioning of such facilities. The Safety Guide has been prepared through a series of Consultants meetings and a Technical Committee meeting

Decommissioning of medical, industrial and research facilities. Safety guide

International Nuclear Information System (INIS)

2005-01-01

Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of medical, industrial and research facilities where radioactive materials and sources are produced, received, used and stored. It is intended to provide guidance to national authorities and operating organizations, particularly to those in developing countries (as such facilities are predominant in these countries), for the planning and safe management of the decommissioning of such facilities. The Safety Guide has been prepared through a series of Consultants meetings and a Technical Committee meeting

Radiation Safety in Industrial Radiography. Specific Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2013-01-01

This Safety Guide provides recommendations for ensuring radiation safety in industrial radiography used in non-destructive testing. This includes industrial radiography work that utilizes X ray and gamma sources, both in shielded facilities that have effective engineering controls and in outside shielded facilities using mobile sources. Contents: 1. Introduction; 2. Duties and responsibilities; 3. Safety assessment; 4. Radiation protection programme; 5. Training and qualification; 6. Individual monitoring of workers; 7. Workplace monitoring; 8. Control of radioactive sources; 9. Safety of industrial radiography sources and exposure devices; 10. Radiography in shielded enclosures; 11. Site radiography; 12. Transport of radioactive sources; 13. Emergency preparedness and response; Appendix: IAEA categorization of radioactive sources; Annex I: Example safety assessment; Annex II: Overview of industrial radiography sources and equipment; Annex III: Examples of accidents in industrial radiography

Radiation Safety in Industrial Radiography. Specific Safety Guide (French Edition)

International Nuclear Information System (INIS)

2013-01-01

This Safety Guide provides recommendations for ensuring radiation safety in industrial radiography used in non-destructive testing. This includes industrial radiography work that utilizes X ray and gamma sources, both in … shielded facilities that have effective engineering controls and in outside shielded facilities using mobile sources. Contents: 1. Introduction; 2. Duties and responsibilities; 3. Safety assessment; 4. Radiation protection programme; 5. Training and qualification; 6. Individual monitoring of workers; 7. Workplace monitoring; 8. Control of radioactive sources; 9. Safety of industrial radiography sources and exposure devices; 10. Radiography in shielded enclosures; 11. Site radiography; 12. Transport of radioactive sources; 13. Emergency preparedness and response; Appendix: IAEA categorization of radioactive sources; Annex I: Example safety assessment; Annex II: Overview of industrial radiography sources and equipment; Annex III: Examples of accidents in industrial radiography

Radiation Safety in Industrial Radiography. Specific Safety Guide (Arabic Edition)

International Nuclear Information System (INIS)

2012-01-01

This Safety Guide provides recommendations for ensuring radiation safety in industrial radiography used in non-destructive testing. This includes industrial radiography work that utilizes X ray and gamma sources, both in shielded facilities that have effective engineering controls and outside shielded facilities using mobile sources. Contents: 1. Introduction; 2. Duties and responsibilities; 3. Safety assessment; 4. Radiation protection programme; 5. Training and qualification; 6. Individual monitoring of workers; 7. Workplace monitoring; 8. Control of radioactive sources; 9. Safety of industrial radiography sources and exposure devices; 10. Radiography in shielded enclosures; 11. Site radiography; 12. Transport of radioactive sources; 13. Emergency preparedness and response; Appendix: IAEA categorization of radioactive sources; Annex I: Example safety assessment; Annex II: Overview of industrial radiography sources and equipment; Annex III: Examples of accidents in industrial radiography.

Design of reactor containment systems for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2008-01-01

This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. It is a revision of the Safety Guide on Design of the Reactor Containment Systems in Nuclear Power Plants (Safety Series No. 50-Sg-D1) issued in 1985 and supplements the Safety Requirements publication on Safety of Nuclear Power Plants: Design. The present Safety Guide was prepared on the basis of a systematic review of the relevant publications, including the Safety of Nuclear Power Plants: Design, the Safety fundamentals publication on The Safety of Nuclear Installations, Safety Guides, INSAG Reports, a Technical Report and other publications covering the safety of nuclear power plants. 1.2. The confinement of radioactive material in a nuclear plant, including the control of discharges and the minimization of releases, is a fundamental safety function to be ensured in normal operational modes, for anticipated operational occurrences, in design basis accidents and, to the extent practicable, in selected beyond design basis accidents. In accordance with the concept of defence in depth, this fundamental safety function is achieved by means of several barriers and levels of defence. In most designs, the third and fourth levels of defence are achieved mainly by means of a strong structure enveloping the nuclear reactor. This structure is called the 'containment structure' or simply the 'containment'. This definition also applies to double wall containments. 1.3. The containment structure also protects the reactor against external events and provides radiation shielding in operational states and accident conditions. The containment structure and its associated systems with the functions of isolation, energy management, and control of radionuclides and combustible gases are referred to as the containment systems

Design of reactor containment systems for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2004-01-01

This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. It is a revision of the Safety Guide on Design of the Reactor Containment Systems in Nuclear Power Plants (Safety Series No. 50-Sg-D1) issued in 1985 and supplements the Safety Requirements publication on Safety of Nuclear Power Plants: Design. The present Safety Guide was prepared on the basis of a systematic review of the relevant publications, including the Safety of Nuclear Power Plants: Design, the Safety fundamentals publication on The Safety of Nuclear Installations, Safety Guides, INSAG Reports, a Technical Report and other publications covering the safety of nuclear power plants. 1.2. The confinement of radioactive material in a nuclear plant, including the control of discharges and the minimization of releases, is a fundamental safety function to be ensured in normal operational modes, for anticipated operational occurrences, in design basis accidents and, to the extent practicable, in selected beyond design basis accidents. In accordance with the concept of defence in depth, this fundamental safety function is achieved by means of several barriers and levels of defence. In most designs, the third and fourth levels of defence are achieved mainly by means of a strong structure enveloping the nuclear reactor. This structure is called the 'containment structure' or simply the 'containment'. This definition also applies to double wall containments. 1.3. The containment structure also protects the reactor against external events and provides radiation shielding in operational states and accident conditions. The containment structure and its associated systems with the functions of isolation, energy management, and control of radionuclides and combustible gases are referred to as the containment systems

Safety design guides for containment extension for CANDU 9

International Nuclear Information System (INIS)

Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young; A. C. D. Wright

1996-03-01

This safety design guide for containment extension describes the containment isolation philosophy and containment extension requirements. The metal extensions and components falling within the scope of ASME Section III are classified in accordance with the CAN/CSA-N285.0 and CAN/CSA-N285.3. The special consideration for the leak monitoring capability, seismic qualification and inspection requirements for containment extensions, etc., are defined in this design guide. In addition, the containment isolation systems are defined and summarized schematically in appendix A. The change status of the regulatory requirements, code and standards should be traced and this safety design guide shall be updated accordingly. (Author) .new

IAEA code and safety guides on quality assurance

International Nuclear Information System (INIS)

Raisic, N.

1980-01-01

In the framework of its programme in safety standards development, the IAEA has recently published a Code of Practice on Quality Assurance for Safety in Nuclear Power Plants. The Code establishes minimum requirements for quality assurance which Member States should use in the context of their own nuclear safety requirements. A series of 10 Safety Guides which describe acceptable methods of implementing the requirements of specific sections of the Code are in preparation. (orig.)

IAEA codes and guides for safety of nuclear power plants

International Nuclear Information System (INIS)

Raisic, N.

1980-01-01

The objectives and scope of the Agency's programme of nuclear safety standards are described and the role of these documents in regulation of nuclear power im Member States is discussed. For each of the five areas of safety standards development, i.e. siting, design, operation, quality assurance and governmental organization, a set of principles underlying requirements and recommendations contained in the Code of Practice and Safety Guides will be presented. Safety Guides in each of the five areas will be reviewed in respect of the scope and content. A consideration will be given to the future development of the safety standards and to the revision and updating of the published documents. (orig./RW)

Decommissioning of nuclear power plants and research reactors. Safety guide

International Nuclear Information System (INIS)

1999-01-01

Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of nuclear power plants and research reactors. It is intended to provide guidance to national authorities and operating organizations for the planning and safe management of the decommissioning of such installations. This Safety Guide has been prepared through a series of Consultants and Technical Committee meetings. It supersedes former Safety Series publications Nos 52, 74 and 105

Decommissioning of nuclear power plants and research reactors. Safety guide

International Nuclear Information System (INIS)

2004-01-01

Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of nuclear power plants and research reactors. It is intended to provide guidance to national authorities and operating organizations for the planning and safe management of the decommissioning of such installations. This Safety Guide has been prepared through a series of Consultants and Technical Committee meetings. It supersedes former Safety Series publications Nos 52, 74 and 105

Decommissioning of nuclear power plants and research reactors. Safety guide

International Nuclear Information System (INIS)

2001-01-01

Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of nuclear power plants and research reactors. It is intended to provide guidance to national authorities and operating organizations for the planning and safe management of the decommissioning of such installations. This Safety Guide has been prepared through a series of Consultants and Technical Committee meetings. It supersedes former Safety Series publications Nos 52, 74 and 105

Regulatory Control of Radiation Sources. Safety Guide (Arabic Edition)

International Nuclear Information System (INIS)

2012-01-01

This Safety Guide is intended to assist States in implementing the requirements established in Safety Standards Series No. GS-R-1, Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety, for a national regulatory infrastructure to regulate any practice involving radiation sources in medicine, industry, research, agriculture and education. The Safety Guide provides advice on the legislative basis for establishing regulatory bodies, including the effective independence of the regulatory body. It also provides guidance on implementing the functions and activities of regulatory bodies: the development of regulations and guides on radiation safety; implementation of a system for notification and authorization; carrying out regulatory inspections; taking necessary enforcement actions; and investigating accidents and circumstances potentially giving rise to accidents. The various aspects relating to the regulatory control of consumer products are explained, including justification, optimization of exposure, safety assessment and authorization. Guidance is also provided on the organization and staffing of regulatory bodies. Contents: 1. Introduction; 2. Legal framework for a regulatory infrastructure; 3. Principal functions and activities of the regulatory body; 4. Regulatory control of the supply of consumer products; 5. Functions of the regulatory body shared with other governmental agencies; 6. Organization and staffing of the regulatory body; 7. Documentation of the functions and activities of the regulatory body; 8. Support services; 9. Quality management for the regulatory system.

Radiation protection and safety guide no. GRPB-G-4: inspection

International Nuclear Information System (INIS)

Schandorf, C.; Darko, O.; Yeboah, J.; Osei, E.K.; Asiamah, S.D.

1995-01-01

The use of ionizing radiation and radiation sources in Ghana is on the increase due to national developmental efforts in Health Care, Food and Agriculture, Industry, Science and Technology. This regulatory Guide has been developed to assist both the Regulatory Body (Radiation Protection Board) and operating organizations to perform systematic inspections commensurate with the level of hazard associated with the application of radiation sources and radioactive materials. The present Guide applies to the Radiation Protection and Safety inspection and/or audit conducted by the Radiation Protection Board or Radiation Safety Officer. The present Guide is applicable in Ghana and to foreign suppliers of radiation sources. The present Guide applies to notifying person, licensee, or registrant and unauthorized practice

Field Test of the World Health Organization Multi-Professional Patient Safety Curriculum Guide

Science.gov (United States)

Farley, Donna; Zheng, Hao; Rousi, Eirini; Leotsakos, Agnès

2015-01-01

Introduction Although the importance of training in patient safety has been acknowledged for over a decade, it remains under-utilized and under-valued in most countries. WHO developed the Multi-professional Patient Safety Curriculum Guide to provide schools with the requirements and tools for incorporating patient safety in education. It was field tested with 12 participating schools across the six WHO regions, to assess its effectiveness for teaching patient safety to undergraduate and graduate students in a global variety of settings. Methods The evaluation used a combined prospective/retrospective design to generate formative information on the experiences of working with the Guide and summative information on the impacts of the Guide. Using stakeholder interviews and student surveys, data were gathered from each participating school at three times: the start of the field test (baseline), soon after each school started teaching, and soon after each school finished teaching. Results Stakeholders interviewed were strongly positive about the Guide, noting that it emphasized universally important patient safety topics, was culturally appropriate for their countries, and gave credibility and created a focus on patient safety at their schools. Student perceptions and attitudes regarding patient safety improved substantially during the field test, and their knowledge of the topics they were taught doubled, from 10.7% to 20.8% of correct answers on the student survey. Discussion This evaluation documented the effectiveness of the Curriculum Guide, for both ease of use by schools and its impacts on improving the patient safety knowledge of healthcare students. WHO should be well positioned to refine the contents of the Guide and move forward in encouraging broader use of the Guide globally for teaching patient safety. PMID:26406893

Field Test of the World Health Organization Multi-Professional Patient Safety Curriculum Guide.

Science.gov (United States)

Farley, Donna; Zheng, Hao; Rousi, Eirini; Leotsakos, Agnès

2015-01-01

Although the importance of training in patient safety has been acknowledged for over a decade, it remains under-utilized and under-valued in most countries. WHO developed the Multi-professional Patient Safety Curriculum Guide to provide schools with the requirements and tools for incorporating patient safety in education. It was field tested with 12 participating schools across the six WHO regions, to assess its effectiveness for teaching patient safety to undergraduate and graduate students in a global variety of settings. The evaluation used a combined prospective/retrospective design to generate formative information on the experiences of working with the Guide and summative information on the impacts of the Guide. Using stakeholder interviews and student surveys, data were gathered from each participating school at three times: the start of the field test (baseline), soon after each school started teaching, and soon after each school finished teaching. Stakeholders interviewed were strongly positive about the Guide, noting that it emphasized universally important patient safety topics, was culturally appropriate for their countries, and gave credibility and created a focus on patient safety at their schools. Student perceptions and attitudes regarding patient safety improved substantially during the field test, and their knowledge of the topics they were taught doubled, from 10.7% to 20.8% of correct answers on the student survey. This evaluation documented the effectiveness of the Curriculum Guide, for both ease of use by schools and its impacts on improving the patient safety knowledge of healthcare students. WHO should be well positioned to refine the contents of the Guide and move forward in encouraging broader use of the Guide globally for teaching patient safety.

Safety, Health, and Environmental Auditing A Practical Guide

CERN Document Server

Pain, Simon Watson

2010-01-01

A practical guide to environmental, safety, and occupational health audits. It allows organizations and business to avoid expensive external auditors and retain the knowledge and learning 'in-house'. It allows any competent manager or safety/environmental officer to undertake in-house audits in a competent and reproducible fashion.

Application of the management system for facilities and activities. Safety guide

International Nuclear Information System (INIS)

2006-01-01

This Safety Guide supports the Safety Requirements publication on The Management System for Facilities and Activities. It provides generic guidance to aid in establishing, implementing, assessing and continually improving a management system that complies with the requirements established. In addition to this Safety Guide, there are a number of Safety Guides for specific technical areas. Together these provide all the guidance necessary for implementing these requirements. This publication supersedes Safety Series No. 50-SG-Q1-Q7 (1996). The guidance provided here may be used by organizations in the following ways: - To assist in the development of the management systems of organizations directly responsible for operating facilities and activities and providing services for: Nuclear facilities; Activities using sources of ionizing radiation; Radioactive waste management; The transport of radioactive material; Radiation protection activities; Any other practices or circumstances in which people may be exposed to radiation from naturally occurring or artificial sources; The regulation of such facilities and activities; - To assist in the development of the management systems of the relevant regulatory bodies; - By the operator, to specify to a supplier, via contractual documentation, any guidance of this Safety Guide that should be included in the supplier's management system for the supply and delivery of products

Safety design guides for environmental qualification for CANDU 9

International Nuclear Information System (INIS)

Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young; A. C. D. Wright

1996-03-01

This safety design guide describes the safety philosophy and requirements for the environmental qualification of safety related systems and components for CANDU 9. The environmental qualification program identifies the equipments to be qualified and conditions to be used for qualification and provides comprehensive set of documentation to ensure that the qualification is complete and can be maintained for the life of the plant. A summary of the system, components and structures requiring environmental qualification is provided in the table for the guidance of the system design, and this table will be subject to change or confirmation by the environmental qualification program. Also, plant ares subject to harsh environment is provided in the figure. The change status of the regulatory requirements, code and standards should be traced and this safety design guide shall be updated accordingly. 1 tab., 5 figs. (Author) .new

Environment, health and safety guiding principles

International Nuclear Information System (INIS)

1997-06-01

The Canadian Energy Pipeline Association (CEPA) has taken a leadership role in promoting responsible planning, management and work practices that meet the pipeline industry's environment, health and safety objectives. This brochure contains CEPA's environment, health and safety statement. It lists the guiding principles developed and endorsed by CEPA and its member companies in support of protecting the environment and the health and safety of its employees and the public. The 11 CEPA member companies are: Alberta Natural Gas Company Ltd., ATCO Gas Services Ltd., Foothills Pipe Lines Ltd., Interprovincial Pipe Line Inc., NOVA Gas Transmission Limited, TransGas Limited, Trans Mountain Pipe Line Company Ltd., Trans-Northern Pipelines Inc., Trans Quebec and Maritimes Pipeline Inc., and Westcoast Energy Inc

Protection of the patient in medical exposure - the related IAEA safety guide

International Nuclear Information System (INIS)

Turai, I.

1999-01-01

The Radiation Safety Section of the Agency has recently completed the draft Safety Guide on Radiation Protection in Medical Exposures' for submission to the Publication Committee of the IAEA. The author as served as one of the scientific secretaries responsible for the preparation and review of this document in the last two years. The drafts of this IAEA Safety Guide have undergone a detailed review process by specialists of 14 Member States and the co-sponsoring organizations, the Pan American Health Organization and the World Health Organization (WHO). The last draft is the primary source of this paper. The Safety Guide will be part of the Safety Standards Series. It is addressed to Regulatory Authorities and other National Institutions to provide them with guidance at the national level on the practical implementation of Appendix II (Medical Exposure) of the International Basic Safety Standards for the Protection against Ionizing Radiation and for the Safety of Radiation Sources

Organization and staffing of the regulatory body for nuclear facilities. Safety guide

International Nuclear Information System (INIS)

2005-01-01

The purpose of this safety guide is to provide recommendations for national authorities on the appropriate management system, organization and staffing for the regulatory body responsible for the regulation of nuclear facilities in order to achieve compliance with the applicable safety requirements. This safety guide covers the organization and staffing in relation to nuclear facilities such as: enrichment and fuel manufacturing plants. Nuclear power plants. Other reactors such as research reactors and critical assemblies. Spent fuel reprocessing plants. And radioactive waste management facilities such as treatment, storage and disposal facilities. This safety guide also covers issues related to the decommissioning of nuclear facilities, the closure of waste disposal facilities and site rehabilitation

Application of the concepts of exclusion, exemption and clearance. Safety guide

International Nuclear Information System (INIS)

2007-01-01

The objective of this Safety Guide is to provide guidance to national authorities, including regulatory bodies, and operating organizations on the application of the concepts of exclusion, exemption and clearance as established in the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (BSS). The Safety Guide includes specific values of activity concentration for both radionuclides of natural origin and those of artificial origin that may be used for bulk amounts of material for the purpose of applying exclusion or exemption. It also elaborates on the possible application of these values to clearance

Evaluation of seismic hazards for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2002-01-01

The main objective of this Safety Guide is to provide recommendations on how to determine the ground motion hazards for a plant at a particular site and the potential for surface faulting, which could affect the feasibility of construction and safe operation of a plant at that site. The guidelines and procedures presented in this Safety Guide can appropriately be used in evaluations of site suitability and seismic hazards for nuclear power plants in any seismotectonic environment. The probabilistic seismic hazard analysis recommended in this Safety Guide also addresses the needs for seismic hazard analysis of external event PSAs conducted for nuclear power plants. Many of the methods and processes described may also be applicable to nuclear facilities other than power plants. Other phenomena of permanent ground displacement (liquefaction, slope instability, subsidence and collapse) as well as the topic of seismically induced flooding are treated in Safety Guides relating to foundation safety and coastal flooding. Recommendations of a general nature are given in Section 2. Section 3 discusses the acquisition of a database containing the information needed to evaluate and address all hazards associated with earthquakes. Section 4 covers the use of this database for construction of a seismotectonic model. Sections 5 and 6 review ground motion hazards and evaluations of the potential for surface faulting, respectively. Section 7 addresses quality assurance in the evaluation of seismic hazards for nuclear power plants

Development and Application of Level 2 Probabilistic Safety Assessment for Nuclear Power Plants. Specific Safety Guide

International Nuclear Information System (INIS)

2010-01-01

The objective of this Safety Guide is to provide recommendations for meeting the IAEA safety requirements in performing or managing a level 2 probabilistic safety assessment (PSA) project for a nuclear power plant; thus it complements the Safety Guide on level 1 PSA. One of the aims of this Safety Guide is to promote a standard framework, standard terms and a standard set of documents for level 2 PSAs to facilitate regulatory and external peer review of their results. It describes all elements of the level 2 PSA that need to be carried out if the starting point is a fully comprehensive level 1 PSA. Contents: 1. Introduction; 2. PSA project management and organization; 3. Identification of design aspects important to severe accidents and acquisition of information; 4. Interface with level 1 PSA: Grouping of sequences; 5. Accident progression and containment analysis; 6. Source terms for severe accidents; 7. Documentation of the analysis: Presentation and interpretation of results; 8. Use and applications of the PSA; Annex I: Example of a typical schedule for a level 2 PSA; Annex II: Computer codes for simulation of severe accidents; Annex III: Sample outline of documentation for a level 2 PSA study.

Core management and fuel handling for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2004-01-01

This Safety Guide supplements and elaborates upon the safety requirements for core management and fuel handling that are presented in Section 5 of the Safety Requirements publication on the operation of nuclear power plants. The present publication supersedes the IAEA Safety Guide on Safety Aspects of Core Management and Fuel Handling, issued in 1985 as Safety Series No. 50-SG-010. It is also related to the Safety Guide on the Operating Organization for Nuclear Power Plants, which identifies fuel management as one of the various functions to be performed by the operating organization. The purpose of this Safety Guide is to provide recommendations for core management and fuel handling at nuclear power plants on the basis of current international good practice. The present Safety Guide addresses those aspects of fuel management activities that are necessary in order to allow optimum reactor core operation without compromising the limits imposed by the design safety considerations relating to the nuclear fuel and the plant as a whole. In this publication, 'core management' refers to those activities that are associated with fuel management in the core and reactivity control, and 'fuel handling' refers to the movement, storage and control of fresh and irradiated fuel. Fuel management comprises both core management and fuel handling. This Safety Guide deals with fuel management for all types of land based stationary thermal neutron power plants. It describes the safety objectives of core management, the tasks that have to be accomplished to meet these objectives and the activities undertaken to perform those tasks. It also deals with the receipt of fresh fuel, storage and handling of fuel and other core components, the loading and unloading of fuel and core components, and the insertion and removal of other reactor materials. In addition, it deals with loading a transport container with irradiated fuel and its preparation for transport off the site. Transport

Core management and fuel handling for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2002-01-01

This Safety Guide supplements and elaborates upon the safety requirements for core management and fuel handling that are presented in Section 5 of the Safety Requirements publication on the operation of nuclear power plants. The present publication supersedes the IAEA Safety Guide on Safety Aspects of Core Management and Fuel Handling, issued in 1985 as Safety Series No. 50-SG-010. It is also related to the Safety Guide on the Operating Organization for Nuclear Power Plants, which identifies fuel management as one of the various functions to be performed by the operating organization. The purpose of this Safety Guide is to provide recommendations for core management and fuel handling at nuclear power plants on the basis of current international good practice. The present Safety Guide addresses those aspects of fuel management activities that are necessary in order to allow optimum reactor core operation without compromising the limits imposed by the design safety considerations relating to the nuclear fuel and the plant as a whole. In this publication, 'core management' refers to those activities that are associated with fuel management in the core and reactivity control, and 'fuel handling' refers to the movement, storage and control of fresh and irradiated fuel. Fuel management comprises both core management and fuel handling. This Safety Guide deals with fuel management for all types of land based stationary thermal neutron power plants. It describes the safety objectives of core management, the tasks that have to be accomplished to meet these objectives and the activities undertaken to perform those tasks. It also deals with the receipt of fresh fuel, storage and handling of fuel and other core components, the loading and unloading of fuel and core components, and the insertion and removal of other reactor materials. In addition, it deals with loading a transport container with irradiated fuel and its preparation for transport off the site. Transport

Design of Instrumentation and Control Systems for Nuclear Power Plants. Specific Safety Guide

International Nuclear Information System (INIS)

2016-01-01

This publication is a revision and combination of two Safety Guides, IAEA Safety Standards Series No. NS-G-1.1 and No. NS-G-1.3. The revision takes into account developments in instrumentation and control (I&C) systems since the publication of the earlier Safety Guides. The main changes relate to the continuing development of computer applications and the evolution of the methods necessary for their safe, secure and practical use. In addition, account is taken of developments in human factors engineering and the need for computer security. This Safety Guide references and takes into account other IAEA Safety Standards and Nuclear Security Series publications that provide guidance relating to I&C design

Department of Energy Construction Safety Reference Guide

Energy Technology Data Exchange (ETDEWEB)

1993-09-01

DOE has adopted the Occupational Safety and Health Administration (OSHA) regulations Title 29 Code of Federal Regulations (CFR) 1926 ``Safety and Health Regulations for Construction,`` and related parts of 29 CFR 1910, ``Occupational Safety and Health Standards.`` This nonmandatory reference guide is based on these OSHA regulations and, where appropriate, incorporates additional standards, codes, directives, and work practices that are recognized and accepted by DOE and the construction industry. It covers excavation, scaffolding, electricity, fire, signs/barricades, cranes/hoists/conveyors, hand and power tools, concrete/masonry, stairways/ladders, welding/cutting, motor vehicles/mechanical equipment, demolition, materials, blasting, steel erection, etc.

Guide to the safety design examination about light water reactor facilities for power generation

International Nuclear Information System (INIS)

Anon.

1977-01-01

This guide was compiled to evaluate the validity of the design policy when the safety design is examined at the time of the application for approval of the installation of nuclear reactors. About 7 years has elapsed since the existing guide was established, and the more appropriate guide to evaluate the safety should be made on the basis of the knowledge and experience accumulated thereafter. The range of application of this guide is limited to the above described evaluation, and it is not intended as the general standard for the design of nuclear reactors. First, the definition of the words used in this guide is given. Then, the guide to the safety examination is described about the general matters of reactor facilities, nuclear reactors and the measuring and controlling system, reactor-stopping system, reactivity-controlling system and safety protection system, reactor-cooling system, reactor containment vessels, fuel handling and waste treatment system. Several matters which require attention in the application of this guide or the clarification of the significance and interpretation of the guide itself were found, therefore the explanation about them was added at the end of this guide. (Kako, I.)

Design of the reactor coolant system and associated systems in nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2008-01-01

This Safety Guide was prepared under the IAEA programme for establishing safety standards for nuclear power plants. The basic requirements for the design of safety systems for nuclear power plants are established in the Safety Requirements publication, Safety Standards Series No. NS-R-1 on Safety of Nuclear Power Plants: Design, which it supplements. This Safety Guide describes how the requirements for the design of the reactor coolant system (RCS) and associated systems in nuclear power plants should be met. 1.2. This publication is a revision and combination of two previous Safety Guides, Safety Series No. 50-SG-D6 on Ultimate Heat Sink and Directly Associated Heat Transport Systems for Nuclear Power Plants (1981), and Safety Series No. 50-SG-D13 on Reactor Coolant and Associated Systems in Nuclear Power Plants (1986), which are superseded by this new Safety Guide. 1.3. The revision takes account of developments in the design of the RCS and associated systems in nuclear power plants since the earlier Safety Guides were published in 1981 and 1986, respectively. The other objectives of the revision are to ensure consistency with Ref., issued in 2000, and to update the technical content. In addition, an appendix on pressurized heavy water reactors (PHWRs) has been included

Nuclear regulatory guides for LWR (PWR) fuel in Japan and some related safety research

International Nuclear Information System (INIS)

Ichikawa, M.

1994-01-01

The general aspects of licensing procedure for NPPs in Japan and regulatory guides are described. The expert committee reports closely related to PWR fuel are reviewed. Some major results of reactor safety research experiments at NSPR (Nuclear Safety Research Reactor of JAERI) used for establishment of related guide, are discussed. It is pointed out that the reactor safety research in Japan supports the regularity activities by establishing and revising guides and preparing the necessary regulatory data as well as improving nuclear safety. 10 figs., 4 refs

Nuclear regulatory guides for LWR (PWR) fuel in Japan and some related safety research

Energy Technology Data Exchange (ETDEWEB)

Ichikawa, M [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)

1994-12-31

The general aspects of licensing procedure for NPPs in Japan and regulatory guides are described. The expert committee reports closely related to PWR fuel are reviewed. Some major results of reactor safety research experiments at NSPR (Nuclear Safety Research Reactor of JAERI) used for establishment of related guide, are discussed. It is pointed out that the reactor safety research in Japan supports the regularity activities by establishing and revising guides and preparing the necessary regulatory data as well as improving nuclear safety. 10 figs., 4 refs.

Protection against internal fires and explosions in the design of nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2004-01-01

Experience of the past two decades in the operation of nuclear power plants and modern analysis techniques confirm that fire may be a real threat to nuclear safety and should receive adequate attention from the beginning of the design process throughout the life of the plant. Within the framework of the NUSS programme, a Safety Guide on fire protection had therefore been developed to enlarge on the general requirements given in the Code. Since its first publication in 1979, there has been considerable development in protection technology and analysis methods and after the Chernobyl accident it was decided to revise the existing Guide. This Safety Guide supplements the requirements established in Safety of Nuclear Power Plants: Design. It supersedes Safety Series No. 50-SG-D2 (Rev. 1), Fire Protection in Nuclear Power Plants: A Safety Guide, issued in 1992.The present Safety Guide is intended to advise designers, safety assessors and regulators on the concept of fire protection in the design of nuclear power plants and on recommended ways of implementing the concept in some detail in practice

Storage of Spent Nuclear Fuel. Specific Safety Guide

International Nuclear Information System (INIS)

2012-01-01

This Safety Guide provides recommendations and guidance on the storage of spent nuclear fuel. It covers all types of storage facilities and all types of spent fuel from nuclear power plants and research reactors. It takes into consideration the longer storage periods that have become necessary owing to delays in the development of disposal facilities and the decrease in reprocessing activities. It also considers developments associated with nuclear fuel, such as higher enrichment, mixed oxide fuels and higher burnup. The Safety Guide is not intended to cover the storage of spent fuel if this is part of the operation of a nuclear power plant or spent fuel reprocessing facility. Guidance is provided on all stages for spent fuel storage facilities, from planning through siting and design to operation and decommissioning, and in particular retrieval of spent fuel. Contents: 1. Introduction; 2. Protection of human health and the environment; 3. Roles and responsibilities; 4. Management system; 5. Safety case and safety assessment; 6. General safety considerations for storage of spent fuel. Appendix I: Specific safety considerations for wet or dry storage of spent fuel; Appendix II: Conditions for specific types of fuel and additional considerations; Annex: I: Short term and long term storage; Annex II: Operational and safety considerations for wet and dry spent fuel storage facilities; Annex III: Examples of sections of operating procedures for a spent fuel storage facility; Annex IV: Site conditions, processes and events for consideration in a safety assessment (external human induced phenomena); Annex V: Site conditions, processes and events for consideration in a safety assessment (external natural phenomena); Annex VI: Site conditions, processes and events for consideration in a safety assessment (external human induced phenomena); Annex VII: Postulated initiating events for consideration in a safety assessment (internal phenomena).

IAEA safety guides in the light of recent developments in earthquake engineering

International Nuclear Information System (INIS)

Gurpinar, A.

1988-11-01

The IAEA safety guides 50-SG-S1 and 50-SG-S2 emphasize on the determination of the design basis earthquake ground motion and earthquake resistant design considerations for nuclear power plants, respectively. Since the elaboration of these safety guides years have elapsed and a review of some of these concepts is necessary, taking into account the information collected and the technical developments. In this article, topics within the scope of these safety guides are discussed. In particular, the results of some recent research which may have a bearing on the nuclear industry are highlighted. Conclusions and recommendations are presented. 6 fig., 19 refs. (F.M.)

Safety Software Guide Perspectives for the Design of New Nuclear Facilities (U)

International Nuclear Information System (INIS)

VINCENT, Andrew

2005-01-01

In June of this year, the Department of Energy (DOE) issued directives DOE O 414.1C and DOE G 414.1-4 to improve quality assurance programs, processes, and procedures among its safety contractors. Specifically, guidance entitled, ''Safety Software Guide for use with 10 CFR 830 Subpart A, Quality Assurance Requirements, and DOE O 414.1C, Quality Assurance, DOE G 414.1-4'', provides information and acceptable methods to comply with safety software quality assurance (SQA) requirements. The guidance provides a roadmap for meeting DOE O 414.1C, ''Quality Assurance'', and the quality assurance program (QAP) requirements of Title 10 Code of Federal Regulations (CFR) 830, Subpart A, Quality Assurance, for DOE nuclear facilities and software application activities. [1, 2] The order and guide are part of a comprehensive implementation plan that addresses issues and concerns documented in Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 2002-1. [3] Safety SQA requirements for DOE as well as National Nuclear Security Administration contractors are necessary to implement effective quality assurance (QA) processes and achieve safe nuclear facility operations. DOE G 414.1-4 was developed to provide guidance on establishing and implementing effective QA processes tied specifically to nuclear facility safety software applications. The Guide includes software application practices covered by appropriate national and international consensus standards and various processes currently in use at DOE facilities. While the safety software guidance is considered to be of sufficient rigor and depth to ensure acceptable reliability of safety software at all DOE nuclear facilities, new nuclear facilities are well suited to take advantage of the guide to ensure compliant programs and processes are implemented. Attributes such as the facility life-cycle stage and the hazardous nature of each facility operations are considered, along with the category and level of importance of the

Le guide de montagne dans les fictions cinématographiques : quelques figures fondatrices et paradigmatiques (1915—1945

Directory of Open Access Journals (Sweden)

Rémy Pithon

2009-08-01

Full Text Available L’article se concentre sur la figure du guide de haute montagne, acteur majeur de l’alpinisme et héros populaire. Depuis la naissance du « Bergfilm » après la première mondiale, du cinéma muet au cinéma parlant, les stéréotypes narratifs et les éléments thématiques en font une figure emblématique du genre cinématographique. Ses qualités morales s’ajoutent à ses prouesses techniques, et ses vertus s’opposent aux vices supposés des gens d’en bas ou de l’étranger.

Assessment of occupational exposure due to external sources of radiation. Safety guide

International Nuclear Information System (INIS)

2000-01-01

Occupational exposure to ionizing radiation can occur in a range of industries, medical institutions, educational and research establishments and nuclear fuel cycle facilities. Adequate radiation protection of workers is essential for the safe and acceptable use of radiation, radioactive materials and nuclear energy. The three Safety Guides on occupational radiation protection are jointly sponsored by the IAEA and the International Labour Office. The Agency gratefully acknowledges the contribution of the European Commission to the development of the present Safety Guide. The present Safety Guide addresses the assessment of exposure due to external sources of radiation in the workplace. Such exposure can result from a number of sources within a workplace, and the monitoring of workers and the workplace in such situations is an integral part of any occupational radiation protection programme. The assessment of exposure due to external radiation sources depends critically upon knowledge of the radiation type and energy and the conditions of exposure. The present Safety Guide reflects the major changes over the past decade in international practice in external dose assessment

Assessment of occupational exposure due to external sources of radiation. Safety guide

International Nuclear Information System (INIS)

2004-01-01

Occupational exposure to ionizing radiation can occur in a range of industries, medical institutions, educational and research establishments and nuclear fuel cycle facilities. Adequate radiation protection of workers is essential for the safe and acceptable use of radiation, radioactive materials and nuclear energy. The three Safety Guides on occupational radiation protection are jointly sponsored by the IAEA and the International Labour Office. The Agency gratefully acknowledges the contribution of the European Commission to the development of the present Safety Guide. The present Safety Guide addresses the assessment of exposure due to external sources of radiation in the workplace. Such exposure can result from a number of sources within a workplace, and the monitoring of workers and the workplace in such situations is an integral part of any occupational radiation protection programme. The assessment of exposure due to external radiation sources depends critically upon knowledge of the radiation type and energy and the conditions of exposure. The present Safety Guide reflects the major changes over the past decade in international practice in external dose assessment

Assessment of occupational exposure due to external sources of radiation. Safety guide

International Nuclear Information System (INIS)

1999-01-01

Occupational exposure to ionizing radiation can occur in a range of industries, medical institutions, educational and research establishments and nuclear fuel cycle facilities. Adequate radiation protection of workers is essential for the safe and acceptable use of radiation, radioactive materials and nuclear energy. The three Safety Guides on occupational radiation protection are jointly sponsored by the IAEA and the International Labour Office. The Agency gratefully acknowledges the contribution of the European Commission to the development of the present Safety Guide. The present Safety Guide addresses the assessment of exposure due to external sources of radiation in the workplace. Such exposure can result from a number of sources within a workplace, and the monitoring of workers and the workplace in such situations is an integral part of any occupational radiation protection programme. The assessment of exposure due to external radiation sources depends critically upon knowledge of the radiation type and energy and the conditions of exposure. The present Safety Guide reflects the major changes over the past decade in international practice in external dose assessment

Countermeasures that work : a highway safety countermeasure guide for state highway safety offices : eighth edition : 2015

Science.gov (United States)

2015-11-01

The guide is a basic reference to assist State Highway Safety Offices in selecting effective, evidence- based : countermeasures for traffic safety problem areas. These areas include: : - Alcohol-and Drug-Impaired Driving; : - Seat Belts and Child Res...

Assessment of occupational exposure due to intakes of radionuclides. Safety guide

International Nuclear Information System (INIS)

2004-01-01

Occupational exposure due to radioactive materials can occur as a result of various human activities. These include work associated with the different stages of the nuclear fuel cycle, the use of radioactive sources in medicine, scientific research, agriculture and industry, and occupations which involve the handling of materials containing enhanced concentrations of naturally occurring radionuclides. In order to control this exposure, it is necessary to be able to assess the magnitude of the doses involved. Three interrelated Safety Guides, prepared jointly by the IAEA and the International Labour Office (ILO), provide guidance on the application of the requirements of the Basic Safety Standards with respect to occupational exposure. Reference [3] gives general advice on the exposure conditions for which monitoring programmes should be set up to assess radiation doses arising from external radiation and from intakes of radionuclides by workers. More specific guidance on the assessment of doses from external sources of radiation can be found in Ref. [4] and the present Safety Guide deals with intakes of radioactive materials. Recommendations related to occupational radiation protection have also been developed by the International Commission on Radiological Protection (ICRP) [5]. These and other current recommendations of the ICRP [6] have been taken into account in preparing this Safety Guide. The purpose of this Safety Guide is to provide guidance for regulatory authorities on conducting assessments of intakes of radioactive material arising from occupational exposure. This Guide will also be useful to those concerned with the planning, management and operation of occupational monitoring programmes, and to those involved in the design of equipment for use in internal dosimetry and workplace monitoring

Assessment of occupational exposure due to intakes of radionuclides. Safety guide

International Nuclear Information System (INIS)

2000-01-01

Occupational exposure due to radioactive materials can occur as a result of various human activities. These include work associated with the different stages of the nuclear fuel cycle, the use of radioactive sources in medicine, scientific research, agriculture and industry, and occupations which involve the handling of materials containing enhanced concentrations of naturally occurring radionuclides. In order to control this exposure, it is necessary to be able to assess the magnitude of the doses involved. Three interrelated Safety Guides, prepared jointly by the IAEA and the International Labour Office (ILO), provide guidance on the application of the requirements of the Basic Safety Standards with respect to occupational exposure. Reference [3] gives general advice on the exposure conditions for which monitoring programmes should be set up to assess radiation doses arising from external radiation and from intakes of radionuclides by workers. More specific guidance on the assessment of doses from external sources of radiation can be found in Ref. [4] and the present Safety Guide deals with intakes of radioactive materials. Recommendations related to occupational radiation protection have also been developed by the International Commission on Radiological Protection (ICRP) [5]. These and other current recommendations of the ICRP [6] have been taken into account in preparing this Safety Guide. The purpose of this Safety Guide is to provide guidance for regulatory authorities on conducting assessments of intakes of radioactive material arising from occupational exposure. This Guide will also be useful to those concerned with the planning, management and operation of occupational monitoring programmes, and to those involved in the design of equipment for use in internal dosimetry and workplace monitoring

Assessment of occupational exposure due to intakes of radionuclides. Safety guide

International Nuclear Information System (INIS)

2001-01-01

Occupational exposure due to radioactive materials can occur as a result of various human activities. These include work associated with the different stages of the nuclear fuel cycle, the use of radioactive sources in medicine, scientific research, agriculture and industry, and occupations which involve the handling of materials containing enhanced concentrations of naturally occurring radionuclides. In order to control this exposure, it is necessary to be able to assess the magnitude of the doses involved. Three interrelated Safety Guides, prepared jointly by the IAEA and the International Labour Office (ILO), provide guidance on the application of the requirements of the Basic Safety Standards with respect to occupational exposure. Reference [3] gives general advice on the exposure conditions for which monitoring programmes should be set up to assess radiation doses arising from external radiation and from intakes of radionuclides by workers. More specific guidance on the assessment of doses from external sources of radiation can be found in Ref. [4] and the present Safety Guide deals with intakes of radioactive materials. Recommendations related to occupational radiation protection have also been developed by the International Commission on Radiological Protection (ICRP) [5]. These and other current recommendations of the ICRP [6] have been taken into account in preparing this Safety Guide. The purpose of this Safety Guide is to provide guidance for regulatory authorities on conducting assessments of intakes of radioactive material arising from occupational exposure. This Guide will also be useful to those concerned with the planning, management and operation of occupational monitoring programmes, and to those involved in the design of equipment for use in internal dosimetry and workplace monitoring

Assessment of occupational exposure due to intakes of radionuclides. Safety guide

International Nuclear Information System (INIS)

2002-01-01

Occupational exposure due to radioactive materials can occur as a result of various human activities. These include work associated with the different stages of the nuclear fuel cycle, the use of radioactive sources in medicine, scientific research, agriculture and industry, and occupations which involve the handling of materials containing enhanced concentrations of naturally occurring radionuclides. In order to control this exposure, it is necessary to be able to assess the magnitude of the doses involved. Three interrelated Safety Guides, prepared jointly by the IAEA and the International Labour Office (ILO), provide guidance on the application of the requirements of the Basic Safety Standards with respect to occupational exposure. Reference [3] gives general advice on the exposure conditions for which monitoring programmes should be set up to assess radiation doses arising from external radiation and from intakes of radionuclides by workers. More specific guidance on the assessment of doses from external sources of radiation can be found in Ref. [4] and the present Safety Guide deals with intakes of radioactive materials. Recommendations related to occupational radiation protection have also been developed by the International Commission on Radiological Protection (ICRP) [5]. These and other current recommendations of the ICRP [6] have been taken into account in preparing this Safety Guide. The purpose of this Safety Guide is to provide guidance for regulatory authorities on conducting assessments of intakes of radioactive material arising from occupational exposure. This Guide will also be useful to those concerned with the planning, management and operation of occupational monitoring programmes, and to those involved in the design of equipment for use in internal dosimetry and workplace monitoring

Assessment of occupational exposure due to intakes of radionuclides. Safety guide

International Nuclear Information System (INIS)

1999-01-01

Occupational exposure due to radioactive materials can occur as a result of various human activities. These include work associated with the different stages of the nuclear fuel cycle, the use of radioactive sources in medicine, scientific research, agriculture and industry, and occupations which involve the handling of materials containing enhanced concentrations of naturally occurring radionuclides. In order to control this exposure, it is necessary to be able to assess the magnitude of the doses involved. Three interrelated Safety Guides, prepared jointly by the IAEA and the International Labour Office (ILO), provide guidance on the application of the requirements of the Basic Safety Standards with respect to occupational exposure. Reference [3] gives general advice on the exposure conditions for which monitoring programmes should be set up to assess radiation doses arising from external radiation and from intakes of radionuclides by workers. More specific guidance on the assessment of doses from external sources of radiation can be found in Ref. [4] and the present Safety Guide deals with intakes of radioactive materials. Recommendations related to occupational radiation protection have also been developed by the International Commission on Radiological Protection (ICRP) [5]. These and other current recommendations of the ICRP [6] have been taken into account in preparing this Safety Guide. The purpose of this Safety Guide is to provide guidance for regulatory authorities on conducting assessments of intakes of radioactive material arising from occupational exposure. This Guide will also be useful to those concerned with the planning, management and operation of occupational monitoring programmes, and to those involved in the design of equipment for use in internal dosimetry and workplace monitoring

Safety design guides for grouping and separation for CANDU 9

International Nuclear Information System (INIS)

Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young; A. C. D. Wright

1996-03-01

This safety design guide for grouping and separation describes the philosophy of physical and functional separation for systems, structures and components in CANDU 9 plants and provides the requirements for the implementation of the philosophy in the detailed plant design. The separation of the safety systems is to ensure that common cause events and functional interconnections between systems do not impair the capability to perform the required safety functions for accident conditions. The separation requirements are also applied to the design by grouping the plant systems into two basic groups. Group 1 includes the power production systems and Group 2 includes the safety related systems required for the mitigation of serious process failure. The Group 2 is further separated into subgroups to ensure that events that could cause failure of a special safety system in one subgroup can be mitigated by the other subgroup. The change status for the regulatory requirements, code and standards should be traced and this safety design guide shall be updated accordingly. 2 tabs., 6 figs. (Author) .new

Safety design guides for grouping and separation for CANDU 9

Energy Technology Data Exchange (ETDEWEB)

Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young [Korea Atomic Energy Research Institute, Daeduk (Korea, Republic of); Wright, A C.D. [Atomic Energy of Canada Ltd., Toronto (Canada)

1996-03-01

This safety design guide for grouping and separation describes the philosophy of physical and functional separation for systems, structures and components in CANDU 9 plants and provides the requirements for the implementation of the philosophy in the detailed plant design. The separation of the safety systems is to ensure that common cause events and functional interconnections between systems do not impair the capability to perform the required safety functions for accident conditions. The separation requirements are also applied to the design by grouping the plant systems into two basic groups. Group 1 includes the power production systems and Group 2 includes the safety related systems required for the mitigation of serious process failure. The Group 2 is further separated into subgroups to ensure that events that could cause failure of a special safety system in one subgroup can be mitigated by the other subgroup. The change status for the regulatory requirements, code and standards should be traced and this safety design guide shall be updated accordingly. 2 tabs., 6 figs. (Author) .new.

Construction for Nuclear Installations. Specific Safety Guide

International Nuclear Information System (INIS)

2015-01-01

This Safety Guide provides recommendations and guidance based on international good practices in the construction of nuclear installations, which will enable construction to proceed with high quality. It can be applied to support the development, implementation and assessment of construction methods and procedures and the identification of good practices for ensuring the quality of the construction to meet the design intent and ensure safety. It will be a useful tool for regulatory bodies, licensees and new entrant countries for nuclear power plants and other nuclear installations

Recruitment, qualification and training of personnel for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

The objective of this Safety Guide is to outline the various factors that should to be considered in order to ensure that the operating organization has a sufficient number of qualified personnel for safe operation of a nuclear power plant. In particular, the objective of this publication is to provide general recommendations on the recruitment and selection of plant personnel and on the training and qualification practices that have been adopted in the nuclear industry since the predecessor Safety Guide was published in 1991. In addition, this Safety Guide seeks to establish a framework for ensuring that all managers and staff employed at a nuclear power plant demonstrate their commitment to the management of safety to high professional standards. This Safety Guide deals specifically with those aspects of qualification and training that are important to the safe operation of nuclear power plants. It provides recommendations on the recruitment, selection, qualification, training and authorization of plant personnel. That is, of all personnel in all safety related functions and at all levels of the plant. Some parts or all of this Safety Guide may also be used, with due adaptation, as a guide to the recruitment, selection, training and qualification of staff for other nuclear installations (such as research reactors or nuclear fuel cycle facilities). Section 2 gives guidance on the recruitment and selection of suitable personnel for a nuclear power plant. Section 3 gives guidance on the establishment of personnel qualification, explains the relationship between qualification and competence, and identifies how competence may be developed through education, experience and training. Section 4 deals with general aspects of the training policy for nuclear power plant personnel: the systematic approach, training settings and methods, initial and continuing training, and the keeping of training records. Section 5 provides guidance on the main aspects of training programmes

Recruitment, qualification and training of personnel for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2002-01-01

The objective of this Safety Guide is to outline the various factors that should to be considered in order to ensure that the operating organization has a sufficient number of qualified personnel for safe operation of a nuclear power plant. In particular, the objective of this publication is to provide general recommendations on the recruitment and selection of plant personnel and on the training and qualification practices that have been adopted in the nuclear industry since the predecessor Safety Guide was published in 1991. In addition, this Safety Guide seeks to establish a framework for ensuring that all managers and staff employed at a nuclear power plant demonstrate their commitment to the management of safety to high professional standards. This Safety Guide deals specifically with those aspects of qualification and training that are important to the safe operation of nuclear power plants. It provides recommendations on the recruitment, selection, qualification, training and authorization of plant personnel; that is, of all personnel in all safety related functions and at all levels of the plant. Some parts or all of this Safety Guide may also be used, with due adaptation, as a guide to the recruitment, selection, training and qualification of staff for other nuclear installations (such as research reactors or nuclear fuel cycle facilities). Section 2 gives guidance on the recruitment and selection of suitable personnel for a nuclear power plant. Section 3 gives guidance on the establishment of personnel qualification, explains the relationship between qualification and competence, and identifies how competence may be developed through education, experience and training. Section 4 deals with general aspects of the training policy for nuclear power plant personnel: the systematic approach, training settings and methods, initial and continuing training, and the keeping of training records. Section 5 provides guidance on the main aspects of training programmes

Radiation protection programmes for the transport of radioactive material. Safety guide

International Nuclear Information System (INIS)

2007-01-01

This Safety Guide provides guidance on meeting the requirements for the establishment of radiation protection programmes (RPPs) for the transport of radioactive material, to optimize radiation protection in order to meet the requirements for radiation protection that underlie the Regulations for the Safe Transport of Radioactive Material. This Guide covers general aspects of meeting the requirements for radiation protection, but does not cover criticality safety or other possible hazardous properties of radioactive material. The annexes of this Guide include examples of RPPs, relevant excerpts from the Transport Regulations, examples of total dose per transport index handled, a checklist for road transport, specific segregation distances and emergency instructions for vehicle operators

An introduction to a new IAEA safety guide: 'ageing management for nuclear power plants'

International Nuclear Information System (INIS)

Pachner, J.; Inagaki, T.; Kang, K.S.

2008-01-01

This paper reports on a new IAEA Safety Guide entitled 'Ageing Management for Nuclear Power Plants' which is currently in an advanced draft form, awaiting approval of publication. The new Safety Guide will be an umbrella document for a comprehensive set of guidance documents on ageing management which have been issued by the IAEA. The Safety Guide first presents basic concepts of ageing management as a common basis for the recommendations on: proactive management of ageing throughout the life cycle of a nuclear power plant (NPP); systematic approach to managing ageing in the operation of NPPs; managing obsolescence; and review of ageing management for long term operation (life extension). The Safety Guide is intended to assist operators in establishing, implementing and improving systematic ageing management programs in NPPs and may be used by regulators in preparing regulatory standards and guides, and in verifying that ageing in nuclear power plants is being effectively managed. (author)

Review and assessment of nuclear facilities by the regulatory body. Safety guide

International Nuclear Information System (INIS)

2004-01-01

The purpose of this Safety Guide is to provide recommendations for regulatory bodies on reviewing and assessing the various safety related submissions made by the operator of a nuclear facility at different stages (siting, design, construction, commissioning, operation and decommissioning or closure) in the facility's lifetime to determine whether the facility complies with the applicable safety objectives and requirements. This Safety Guide covers the review and assessment of submissions in relation to the safety of nuclear facilities such as: enrichment and fuel manufacturing plants. Nuclear power plants. Other reactors such as research reactors and critical assemblies. Spent fuel reprocessing plants. And facilities for radioactive waste management, such as treatment, storage and disposal facilities. This Safety Guide also covers issues relating to the decommissioning of nuclear facilities, the closure of waste disposal facilities and site rehabilitation. Objectives, management, planning and organizational matters relating to the review and assessment process are presented in Section 2. Section 3 deals with the bases for decision making and conduct of the review and assessment process. Section 4 covers aspects relating to the assessment of this process. The Appendix provides a generic list of topics to be covered in the review and assessment process

Review and assessment of nuclear facilities by the regulatory body. Safety guide

International Nuclear Information System (INIS)

2005-01-01

The purpose of this Safety Guide is to provide recommendations for regulatory bodies on reviewing and assessing the various safety related submissions made by the operator of a nuclear facility at different stages (siting, design, construction, commissioning, operation and decommissioning or closure) in the facility's lifetime to determine whether the facility complies with the applicable safety objectives and requirements. This Safety Guide covers the review and assessment of submissions in relation to the safety of nuclear facilities such as: enrichment and fuel manufacturing plants. Nuclear power plants. Other reactors such as research reactors and critical assemblies. Spent fuel reprocessing plants. And facilities for radioactive waste management, such as treatment, storage and disposal facilities. This Safety Guide also covers issues relating to the decommissioning of nuclear facilities, the closure of waste disposal facilities and site rehabilitation. Objectives, management, planning and organizational matters relating to the review and assessment process are presented in Section 2. Section 3 deals with the bases for decision making and conduct of the review and assessment process. Section 4 covers aspects relating to the assessment of this process. The Appendix provides a generic list of topics to be covered in the review and assessment process

Safety critical systems handbook a straightforward guide to functional safety : IEC 61508 (2010 edition) and related standards

CERN Document Server

Smith, David J

2010-01-01

Electrical, electronic and programmable electronic systems increasingly carry out safety functions to guard workers and the public against injury or death and the environment against pollution. The international functional safety standard IEC 61508 was revised in 2010, and this is the first comprehensive guide available to the revised standard. As functional safety is applicable to many industries, this book will have a wide readership beyond the chemical and process sector, including oil and gas, power generation, nuclear, aircraft, and automotive industries, plus project, instrumentation, design, and control engineers. * The only comprehensive guide to IEC 61508, updated to cover the 2010 amendments, that will ensure engineers are compliant with the latest process safety systems design and operation standards* Helps readers understand the process required to apply safety critical systems standards* Real-world approach helps users to interpret the standard, with case studies and best practice design examples...

Fire Safety. Managing School Facilities, Guide 6.

Science.gov (United States)

Department for Education and Employment, London (England). Architects and Building Branch.

This booklet discusses how United Kingdom schools can manage fire safety and minimize the risk of fire. The guide examines what legislation school buildings must comply with and covers the major risks. It also describes training and evacuation procedures and provides guidance on fire precautions, alarm systems, fire fighting equipment, and escape…

The Management System for Nuclear Installations Safety Guide

International Nuclear Information System (INIS)

2009-01-01

This Safety Guide is applicable throughout the lifetime of a nuclear installation, including any subsequent period of institutional control, until there is no significant residual radiation hazard. For a nuclear installation, the lifetime includes site evaluation, design, construction, commissioning, operation and decommissioning. These stages in the lifetime of a nuclear installation may overlap. This Safety Guide may be applied to nuclear installations in the following ways: (a)To support the development, implementation, assessment and improvement of the management system of those organizations responsible for research, site evaluation, design, construction, commissioning, operation and decommissioning of a nuclear installation; (b)As an aid in the assessment by the regulatory body of the adequacy of the management system of a nuclear installation; (c)To assist an organization in specifying to a supplier, via contractual documentation, any specific element that should be included within the supplier's management system for the supply of products. This Safety Guide follows the structure of the Safety Requirements publication on The Management System for Facilities and Activities, whereby: (a)Section 2 provides recommendations on implementing the management system, including recommendations relating to safety culture, grading and documentation. (b)Section 3 provides recommendations on the responsibilities of senior management for the development and implementation of an effective management system. (c)Section 4 provides recommendations on resource management, including guidance on human resources, infrastructure and the working environment. (d)Section 5 provides recommendations on how the processes of the installation can be specified and developed, including recommendations on some generic processes of the management system. (e)Section 6 provides recommendations on the measurement, assessment and improvement of the management system of a nuclear installation. (f

Design of the reactor coolant system and associated systems in nuclear power plants. Safety guide (Spanish Edition)

International Nuclear Information System (INIS)

2010-01-01

This Safety Guide was prepared under the IAEA programme for establishing safety standards for nuclear power plants. The basic requirements for the design of safety systems for nuclear power plants are established in the Safety Requirements publication, Safety Standards Series No. NS-R-1 on Safety of Nuclear Power Plants: Design, which it supplements. This Safety Guide describes how the requirements for the design of the reactor coolant system (RCS) and associated systems in nuclear power plants should be met. This publication is a revision and combination of two previous Safety Guides, Safety Series No. 50-SG-D6 on Ultimate Heat Sink and Directly Associated Heat Transport Systems for Nuclear Power Plants (1982), and Safety Series No. 50-SG-D13 on Reactor Coolant and Associated Systems in Nuclear Power Plants (1987), which are superseded by this new Safety Guide. The revision takes account of developments in the design of the RCS and associated systems in nuclear power plants since the earlier Safety Guides were published in 1982 and 1987, respectively. The other objectives of the revision are to ensure consistency with Ref., issued in 2004, and to update the technical content. In addition, an appendix on pressurized heavy water reactors (PHWRs) has been included.

IAEA program for the preparation of safety codes and guides for nuclear power plants

International Nuclear Information System (INIS)

1975-01-01

On the 13th of September, 1974, the IAEA Governors' Council has given its consent to the programme for the establishment of safety codes and guides (annex VII to IAEA document G.C. (XVIII/526)). The programme envisages the establishment of one code of practice for each of the issues governmental organization, siting, design, operation and quality assurance and also of about 50 safety guides between 1975 and 1980. These codes will contain the minimum requirements for the safety of the nuclear power stations, their systems and components. The guides will recommend methods to achieve the aims stated in the codes. It is the purpose of these IAEA activities to provide recommendations and guiding rules which may serve as standards for the assessment of the safety of nuclear power stations for all nations which may become participants in the peaceful use of nuclear energy within the next few years. (orig./AK) [de

Radiation protection aspects of design for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

. The IAEA takes seriously the enduring challenge for users and regulators everywhere: that of ensuring a high level of safety in the use of nuclear materials and radiation sources around the world. Their continuing utilization for the benefit of humankind must be managed in a safe manner, and the IAEA safety standards are designed to facilitate the achievement of that goal. This Safety Guide has been prepared as a part of the IAEA programme on safety standards for nuclear power plants. It includes recommendations on how to satisfy the requirements established in the Safety Requirements publication on the Safety of Nuclear Power Plants: Design. It addresses the provisions that should be made in the design of nuclear power plants in order to protect site personnel, the public and the environment against radiological hazards for operational states, decommissioning and accident conditions. The recommendations on radiation protection provided in this Safety Guide are consistent with the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (BSS), which were jointly sponsored by the Food and Agriculture Organization of the United Nations (FAO), the IAEA, the International Labour Organisation (ILO), the OECD Nuclear Energy Agency (OECD/NEA), the Pan American Health Organization (PAHO) and the World Health Organization (WHO). This Safety Guide supersedes Safety Series No. 50-SG-D9, Design Aspects of Radiation Protection for Nuclear Power Plants, published in 1985. Effective radiation protection is a combination of good design, high quality construction and proper operation. Procedures that address the radiation protection aspects of operation are covered in the Safety Guide on Radiation Protection and Radioactive Waste Management in the operation of Nuclear Power Plants

For safety in procurement, follow the guide!

CERN Multimedia

HSE Unit

2014-01-01

At one time or another, whether as part of a project or for an activity or service, you may find that you have to write a technical specification before placing an order for equipment or machinery. In all cases, when specifying what you need, you must make sure that aspects linked to safety and, in some cases, radiation protection and the protection of the environment, are taken into account in your invitation to tender/price enquiry.   In order to help you with this, the HSE Unit has just published Safety Guideline GS 0-0-1: “27 Key Questions to Ensure that Safety Aspects are Integrated into Invitations to Tender". This guide, available on EDMS under document number 1334815, has been drawn up after the verification of safety aspects of over 300 invitations to tender recently issued by CERN. It collates the most commonly received comments and remarks concerning safety in a question-and-answer format, so you will find plenty of explanations and points to include in your doc...

Lean Six-Sigma in Aviation Safety: An implementation guide for measuring aviation system’s safety performance

OpenAIRE

Panagopoulos, I.; Atkin, C.J.; Sikora, I.

2016-01-01

The paper introduces a conceptual framework that could improve the safety performance measurement process and ultimately the aviation system safety performance. The framework provides an implementation guide on how organisations could design and develop a proactive, measurement tool for assessing and measuring the Acceptable Level of Safety Performance (ALoSP) at sigma (σ) level, a statistical measurement unit. In fact, the methodology adapts and combines quality management tools, a leading i...

Compliance assurance for the safe transport of radioactive material. Safety guide

International Nuclear Information System (INIS)

2009-01-01

The objectives of this Safety Guide are to assist competent authorities in the development and maintenance of compliance assurance programmes in connection with the transport of radioactive material, and to assist applicants, licensees and organizations in their interactions with competent authorities. In order to increase cooperation between competent authorities and to promote the uniform application of international regulations and recommendations, it is desirable to adopt a common approach to regulatory activities. This Safety Guide is intended to assist in accomplishing such a uniform application by recommending most of the actions for which competent authorities need to provide in their programmes for ensuring compliance with the Transport Regulations. This Safety Guide addresses radiation safety aspects of the transport of radioactive material; that is, the subjects that are covered by the Transport Regulations. Radioactive material may have other dangerous properties, however, such as explosiveness, flammability, pyrophoricity, chemical toxicity and corrosiveness; these properties are required to be taken into account in the regulatory control of the design and transport of packages. Physical protection and systems for accounting for and control of nuclear material are also discussed in this Safety Guide. These subjects are not within the scope of the Transport Regulations, but information on them is included here because they must be taken into account in the overall regulatory control of transport, especially when the regulatory framework is being established. Section 1 informs about the background, the objective, the scope and the structure of this publication. Section 2 provides recommendations on the responsibilities and functions of the competent authority. Section 3 provides information on the various national and international regulations and guides for the transport of radioactive material. Section 4 provides recommendations on carrying out

Communication and Consultation with Interested Parties by the Regulatory Body. General Safety Guide

International Nuclear Information System (INIS)

2017-01-01

This Safety Guide provides recommendations on meeting the safety requirements concerning communication and consultation with the public and other interested parties by the regulatory body about the possible radiation risks associated with facilities and activities, and about processes and decisions of the regulatory body. The Safety Guide can be used by authorized parties in circumstances where there are regulatory requirements placed on them for communication and consultation. It may also be used by other organizations or individuals considering their responsibilities for communication and consultation with interested parties.

Co-operative development of nuclear safety regulations, guides and standards based on NUSS

International Nuclear Information System (INIS)

Pachner, J.; Boyd, F.C.; Yaremy, E.M.

1985-01-01

A major need of developing Member States building nuclear power plants (NPPs) of foreign origin is to acquire a capability to regulate such nuclear plants independently. Among other things, this requires the development of national nuclear safety regulations, guides and standards to govern the development and use of nuclear technology. Recognizing the importance and complexity of this task, it seems appropriate that the NPP-exporting Member States share their experience and assist the NPP-importing Member States in the development of their national regulations and guides. In 1983, the Atomic Energy Control Board and Atomic Energy of Canada Ltd. conducted a study of a possible joint programme involving Canada, an NPP-importing Member State and the IAEA for the development of the national nuclear safety regulations and guides based on NUSS documents. During the study, a work plan with manpower estimates for the development of design regulations, safety guides and a guide for regulatory evaluation of design was prepared as an investigatory exercise. The work plan suggests that a successful NUSS implementation in developing Member States will require availability of significant resources at the start of the programme. The study showed that such a joint programme could provide an effective mechanism for transfer of nuclear safety know-how to the developing Member States through NUSS implementation. (author)

Probabilistic safety analysis procedures guide, Sections 8-12. Volume 2, Rev. 1

International Nuclear Information System (INIS)

McCann, M.; Reed, J.; Ruger, C.; Shiu, K.; Teichmann, T.; Unione, A.; Youngblood, R.

1985-08-01

A procedures guide for the performance of probabilistic safety assessment has been prepared for interim use in the Nuclear Regulatory Commission programs. It will be revised as comments are received, and as experience is gained from its use. The probabilistic safety assessment studies performed are intended to produce probabilistic predictive models that can be used and extended by the utilities and by NRC to sharpen the focus of inquiries into a range of issues affecting reactor safety. The first volume of the guide describes the determination of the probability (per year) of core damage resulting from accident initiators internal to the plant (i.e., intrinsic to plant operation) and from loss of off-site electric power. The scope includes human reliability analysis, a determination of the importance of various core damage accident sequences, and an explicit treatment and display of uncertainties for key accident sequences. This second volume deals with the treatment of the so-called external events including seismic disturbances, fires, floods, etc. Ultimately, the guide will be augmented to include the plant-specific analysis of in-plant processes (i.e., containment performance). This guide provides the structure of a probabilistic safety study to be performed, and indicates what products of the study are valuable for regulatory decision making. For internal events, methodology is treated in the guide only to the extent necessary to indicate the range of methods which is acceptable; ample reference is given to alternative methodologies which may be utilized in the performance of the study. For external events, more explicit guidance is given

Safety design guide for pipe rupture protection for CANDU 9

International Nuclear Information System (INIS)

Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young; A. C. D. Wright

1996-03-01

This safety design guide for pipe rupture protection identifies high-energy systems in which pipe ruptures must be postulated to occur, as well as systems that must be protected from the dynamic effects of such ruptures. Dynamic effects considered in this SDG consist of pipe whip (including missiles generated by pipe ruptures, if any) and jet impingement, Requirements for protection against the dynamic effects of a postulated pipe rupture and method of protection of essential structures, systems and components are specified for these effects. The change status for the regulatory requirements, code and standards should be traced and this safety design guide shall be updated accordingly. 2 tabs., 5 refs. (Author) .new

Non-compliance with agrochemical safety guides and associated ...

African Journals Online (AJOL)

Although several occupational health hazards are associated with farming, cocoa farmers could be exposed to more health hazards through use of agrochemicals. The objective of this study was to analyze the effect of non-compliance with agrochemical safety guides on health risks of farmers. The data were collected from ...

The art of appropriate evaluation : a guide for highway safety program managers

Science.gov (United States)

2008-08-01

The guide, updated from its original release in 1999, is intended for project managers who will oversee the evaluation of traffic safety programs. It describes the benefits of evaluation and provides an overview of the steps involved. The guide inclu...

Maintenance, surveillance and in-service inspection in nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2002-01-01

Effective maintenance, surveillance and in-service inspection (MS and I) are essential for the safe operation of a nuclear power plant. The objective of this Safety Guide is to provide recommendations and guidance for MS and I activities to ensure that SSCs important to safety are available to perform their functions in accordance with the assumptions and intent of the design. This Safety Guide covers the organizational and procedural aspects of MS and I. However, it does not give detailed technical advice in relation to particular items of plant equipment, nor does it cover inspections made for and/or by the regulatory body. This Safety Guide provides recommendations and guidance for preventive and remedial measures, including testing, surveillance and in-service inspection, that are necessary to ensure that all plant structures, systems and components (SSCs) important to safety are capable of performing as intended. This Safety Guide covers measures for fulfilling the organizational and administrative requirements for: establishing and implementing schedules for preventive and predictive maintenance, repairing defective plant items, selecting and training personnel, providing related facilities and equipment, procuring stores and spare parts, and generating, collecting and retaining maintenance records for establishing and implementing an adequate feedback system for information on maintenance. MS and I should be subject to quality assurance in relation to all aspects important to safety. Quality assurance has been dealt with in detail in other IAEA safety standards and is covered here only in specific instances, for emphasis. In Section 2, a concept of MS and I is presented and the interrelationship between maintenance, surveillance and inspection is discussed. Section 3 concerns the functions and responsibilities of different organizations involved in MS and I activities. Section 4 provides recommendations and guidance on such organizational aspects as

Maintenance, surveillance and in-service inspection in nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

Effective maintenance, surveillance and in-service inspection (MS and I) are essential for the safe operation of a nuclear power plant. The objective of this Safety Guide is to provide recommendations and guidance for MS and I activities to ensure that SSCs important to safety are available to perform their functions in accordance with the assumptions and intent of the design. This Safety Guide covers the organizational and procedural aspects of MS and I. However, it does not give detailed technical advice in relation to particular items of plant equipment, nor does it cover inspections made for and/or by the regulatory body. This Safety Guide provides recommendations and guidance for preventive and remedial measures, including testing, surveillance and in-service inspection, that are necessary to ensure that all plant structures, systems and components (SSCs) important to safety are capable of performing as intended. This Safety Guide covers measures for fulfilling the organizational and administrative requirements for: establishing and implementing schedules for preventive and predictive maintenance, repairing defective plant items, selecting and training personnel, providing related facilities and equipment, procuring stores and spare parts, and generating, collecting and retaining maintenance records for establishing and implementing an adequate feedback system for information on maintenance. MS and I should be subject to quality assurance in relation to all aspects important to safety. Quality assurance has been dealt with in detail in other IAEA safety standards and is covered here only in specific instances, for emphasis. In Section 2, a concept of MS and I is presented and the interrelationship between maintenance, surveillance and inspection is discussed. Section 3 concerns the functions and responsibilities of different organizations involved in MS and I activities. Section 4 provides recommendations and guidance on such organizational aspects as

Guide de classification: Jeux Paralympiques Londres 2012

OpenAIRE

2013-01-01

Le guide de classification pour les Jeux Paralympiques de Londres 2012 est destiné à informer les Comités Nationaux Paralympiques (CNP) et les Fédérations Internationales des Sports Paralympiques (FISP) sur les politiques et les procédures de classification qui s’appliqueront aux Jeux Paralympiques de Londres 2012.

Safety in the Utilization and Modification of Research Reactors. Specific Safety Guide

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-07-15

This Safety Guide is a revision of Safety Series No. 35-G2 on safety in the utilization and modification of research reactors. It provides recommendations on meeting the requirements for the categorization, safety assessment and approval of research reactor experiments and modification projects. Specific safety considerations in different phases of utilization and modification projects are covered, including the pre-implementation, implementation and post-implementation phases. Guidance is also provided on the operational safety of experiments, including in the handling, dismantling, post-irradiation examination and disposal of experimental devices. Examples of the application of the safety categorization process for experiments and modification projects and of the content of the safety analysis report for an experiment are also provided. Contents: 1. Introduction; 2. Management system for the utilization and modification of a research reactor; 3. Categorization, safety assessment and approval of an experiment or modification; 4. Safety considerations for the design of an experiment or modification; 5. Pre-implementation phase of a modification or utilization project; 6. Implementation phase of a modification or utilization project; 7. Post-implementation phase of a utilization or modification project; 8. Operational safety of experiments at a research reactor; 9. Safety considerations in the handling, dismantling, post-irradiation examination and disposal of experimental devices; 10. Safety aspects of out-of-reactor-core installations; Annex I: Example of a checklist for the categorization of an experiment or modification at a research reactor; Annex II: Example of the content of the safety analysis report for an experiment at a research reactor; Annex III: Examples of reasons for a modification at a research reactor.

Safety in the Utilization and Modification of Research Reactors. Specific Safety Guide

International Nuclear Information System (INIS)

2012-01-01

This Safety Guide is a revision of Safety Series No. 35-G2 on safety in the utilization and modification of research reactors. It provides recommendations on meeting the requirements for the categorization, safety assessment and approval of research reactor experiments and modification projects. Specific safety considerations in different phases of utilization and modification projects are covered, including the pre-implementation, implementation and post-implementation phases. Guidance is also provided on the operational safety of experiments, including in the handling, dismantling, post-irradiation examination and disposal of experimental devices. Examples of the application of the safety categorization process for experiments and modification projects and of the content of the safety analysis report for an experiment are also provided. Contents: 1. Introduction; 2. Management system for the utilization and modification of a research reactor; 3. Categorization, safety assessment and approval of an experiment or modification; 4. Safety considerations for the design of an experiment or modification; 5. Pre-implementation phase of a modification or utilization project; 6. Implementation phase of a modification or utilization project; 7. Post-implementation phase of a utilization or modification project; 8. Operational safety of experiments at a research reactor; 9. Safety considerations in the handling, dismantling, post-irradiation examination and disposal of experimental devices; 10. Safety aspects of out-of-reactor-core installations; Annex I: Example of a checklist for the categorization of an experiment or modification at a research reactor; Annex II: Example of the content of the safety analysis report for an experiment at a research reactor; Annex III: Examples of reasons for a modification at a research reactor.

Safe adventures. An ethnographic study of safety and adventure guides in Arctic Norway

OpenAIRE

Johannessen, Mats Hoel

2016-01-01

With numerous entrepreneurs already established within the area, adventure tourism is a growing industry within Arctic Norway. The continuously expanding interest for the phenomenon has gained universities’ attention with recent education programs for guides being established. A cultural change involving a more professionalized approach to adventure tourism has also been noticed. At the forefront of ensuring tourists’ safety are the guides, who work in the area. In former research on safety i...

Radiation protection aspects in the design of nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2008-01-01

. The IAEA takes seriously the enduring challenge for users and regulators everywhere: that of ensuring a high level of safety in the use of nuclear materials and radiation sources around the world. Their continuing utilization for the benefit of humankind must be managed in a safe manner, and the IAEA safety standards are designed to facilitate the achievement of that goal. This Safety Guide has been prepared as a part of the IAEA programme on safety standards for nuclear power plants. It includes recommendations on how to satisfy the requirements established in the Safety Requirements publication on the Safety of Nuclear Power Plants: Design. It addresses the provisions that should be made in the design of nuclear power plants in order to protect site personnel, the public and the environment against radiological hazards for operational states, decommissioning and accident conditions. The recommendations on radiation protection provided in this Safety Guide are consistent with the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (BSS), which were jointly sponsored by the Food and Agriculture Organization of the United Nations (FAO), the IAEA, the International Labour Organisation (ILO), the OECD Nuclear Energy Agency (OECD/NEA), the Pan American Health Organization (PAHO) and the World Health Organization (WHO). This Safety Guide supersedes Safety Series No. 50-SG-D9, Design Aspects of Radiation Protection for Nuclear Power Plants, published in 1985. Effective radiation protection is a combination of good design, high quality construction and proper operation. Procedures that address the radiation protection aspects of operation are covered in the Safety Guide on Radiation Protection and Radioactive Waste Management in the operation of Nuclear Power Plants

Modèles types de lettres et courriers électroniques

CERN Document Server

Fayet, Michelle

2008-01-01

Bien rédiger les lettres et mails professionnels renforce l'image de qualité de votre entreprise. La 2e édition de ce livre vous offre les clés essentielles pour améliorer la rédaction de votre courrier professionnel et vous propose, par le CD-Rom joint, des modèles de lettres et e-mails directement utilisables. Ils couvrent les situations les plus courantes rencontrées quotidiennement dans une entreprise : les demandes de renseignements, les commandes, les livraisons, les facturations, le recrutement, la gestion du personnel, les échanges avec les partenaires, les banques, les administrations. Indispensable pour rédiger des courriers efficaces, ce guide est un outil de travail incontournable pour tous salariés en charge de la rédaction du courrier, et particulièrement pour les secrétaires et assistantes.

Seismic Hazards in Site Evaluation for Nuclear Installations. Specific Safety Guide

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-08-15

This Safety Guide was prepared under the IAEA programme for safety standards for nuclear installations. It supplements the Safety Requirements publication on Site Evaluation for Nuclear Installations. The present publication provides guidance and recommends procedures for the evaluation of seismic hazards for nuclear power plants and other nuclear installations. It supersedes Evaluation of Seismic Hazards for Nuclear Power Plants, IAEA Safety Standards Series No. NS-G-3.3 (2002). In this publication, the following was taken into account: the need for seismic hazard curves and ground motion spectra for the probabilistic safety assessment of external events for new and existing nuclear installations; feedback of information from IAEA reviews of seismic safety studies for nuclear installations performed over the previous decade; collective knowledge gained from recent significant earthquakes; and new approaches in methods of analysis, particularly in the areas of probabilistic seismic hazard analysis and strong motion simulation. In the evaluation of a site for a nuclear installation, engineering solutions will generally be available to mitigate, by means of certain design features, the potential vibratory effects of earthquakes. However, such solutions cannot always be demonstrated to be adequate for mitigating the effects of phenomena of significant permanent ground displacement such as surface faulting, subsidence, ground collapse or fault creep. The objective of this Safety Guide is to provide recommendations and guidance on evaluating seismic hazards at a nuclear installation site and, in particular, on how to determine: (a) the vibratory ground motion hazards, in order to establish the design basis ground motions and other relevant parameters for both new and existing nuclear installations; and (b) the potential for fault displacement and the rate of fault displacement that could affect the feasibility of the site or the safe operation of the installation at

Geotechnical aspects of site evaluation and foundations for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2003-01-01

This publication is a revision of the former safety standards of IAEA Safety Series No. 50-SG-S8. The scope has been extended to cover not only foundations but also design questions related to geotechnical science and engineering, such as the bearing capacity of foundations, design of earth structures and design of buried structures. Seismic aspects also play an important role in this field, and consequently the Safety Guide on Evaluation of Seismic Hazards for Nuclear Power Plants, Safety Standards Series No. NS-G-3.3, which discusses the determination of seismic input motion, is referenced on several occasions. The present Safety Guide provides an interpretation of the Safety Requirements on Site Evaluation for Nuclear Installations and guidance on how to implement them. It is intended for the use of safety assessors or regulators involved in the licensing process as well as the designers of nuclear power plants, and it provides them with guidance on the methods and procedures for analyses to support the assessment of the geotechnical aspects of the safety of nuclear power plants

Geotechnical aspects of site evaluation and foundations for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2006-01-01

This publication is a revision of the former safety standards of IAEA Safety Series No. 50-SG-S8. The scope has been extended to cover not only foundations but also design questions related to geotechnical science and engineering, such as the bearing capacity of foundations, design of earth structures and design of buried structures Seismic aspects also play an important role in this field, and consequently the Safety Guide on Evaluation of Seismic Hazards for Nuclear Power Plants, Safety Standards Series No. NS-G-3.3, which discusses the determination of seismic input motion, is referenced on several occasions. The present Safety Guide provides an interpretation of the Safety Requirements on Site Evaluation for Nuclear Installations and guidance on how to implement them. It is intended for the use of safety assessors or regulators involved in the licensing process as well as the designers of nuclear power plants, and it provides them with guidance on the methods and procedures for analyses to support the assessment of the geotechnical aspects of the safety of nuclear power plants

Building competence in radiation protection and the safe use of radiation sources. Safety guide

International Nuclear Information System (INIS)

2005-01-01

An essential element of a national infrastructure for radiation protection and safety is the maintenance of an adequate number of competent personnel. This Safety Guide makes recommendations concerning the building of competence in protection and safety, which relate to the training and assessment of qualification of new personnel and retraining of existing personnel in order to develop and maintain appropriate levels of competence. This Safety Guide addresses training in protection and safety aspects in relation to all practices and intervention situations in nuclear and radiation related technologies. This document covers the following aspects: the categories of persons to be trained. The requirements for education, training and experience for each category. The processes of qualification and authorization of persons. A national strategy for building competence

Radiation Safety in Industrial Radiography. Specific Safety Guide (French Edition); Surete radiologique en radiographie industrielle

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-05-15

This Safety Guide provides recommendations for ensuring radiation safety in industrial radiography used in non-destructive testing. This includes industrial radiography work that utilizes X ray and gamma sources, both in Horizontal-Ellipsis shielded facilities that have effective engineering controls and in outside shielded facilities using mobile sources. Contents: 1. Introduction; 2. Duties and responsibilities; 3. Safety assessment; 4. Radiation protection programme; 5. Training and qualification; 6. Individual monitoring of workers; 7. Workplace monitoring; 8. Control of radioactive sources; 9. Safety of industrial radiography sources and exposure devices; 10. Radiography in shielded enclosures; 11. Site radiography; 12. Transport of radioactive sources; 13. Emergency preparedness and response; Appendix: IAEA categorization of radioactive sources; Annex I: Example safety assessment; Annex II: Overview of industrial radiography sources and equipment; Annex III: Examples of accidents in industrial radiography.

Classification of Radioactive Waste. General Safety Guide

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-11-15

This publication is a revision of an earlier Safety Guide of the same title issued in 1994. It recommends revised waste management strategies that reflect changes in practices and approaches since then. It sets out a classification system for the management of waste prior to disposal and for disposal, driven by long term safety considerations. It includes a number of schemes for classifying radioactive waste that can be used to assist with planning overall national approaches to radioactive waste management and to assist with operational management at facilities. Contents: 1. Introduction; 2. The radioactive waste classification scheme; Appendix: The classification of radioactive waste; Annex I: Evolution of IAEA standards on radioactive waste classification; Annex II: Methods of classification; Annex III: Origin and types of radioactive waste.

Classification of Radioactive Waste. General Safety Guide

International Nuclear Information System (INIS)

2009-01-01

This publication is a revision of an earlier Safety Guide of the same title issued in 1994. It recommends revised waste management strategies that reflect changes in practices and approaches since then. It sets out a classification system for the management of waste prior to disposal and for disposal, driven by long term safety considerations. It includes a number of schemes for classifying radioactive waste that can be used to assist with planning overall national approaches to radioactive waste management and to assist with operational management at facilities. Contents: 1. Introduction; 2. The radioactive waste classification scheme; Appendix: The classification of radioactive waste; Annex I: Evolution of IAEA standards on radioactive waste classification; Annex II: Methods of classification; Annex III: Origin and types of radioactive waste

The NUSS safety guides in design and the use of computers

International Nuclear Information System (INIS)

Fischer, J.

1986-01-01

After a brief summary of the NUSS programme, the two design guides are discussed which deal with instrumentation and control circuitry. The potential use of computers is covered differently in these guides because of the historical development and more importantly because of the difference in importance to safety of the I and C systems which are dealt with in these papers. The Agency would consider modifications to the existing guides only when sufficient consensus about the use of computers would warrant a revision of the documents. (author)

Conduct of Operations at Nuclear Power Plants. Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2012-01-01

This Safety Guide identifies the main responsibilities and practices of nuclear power plant (NPP) operations departments in relation to their responsibility for the safe functioning of the plant. The guide presents the factors to be considered in structuring the operations department of an NPP; setting high standards of performance; making safety related decisions in an effective manner; conducting control room and field activities in a thorough and professional manner; and maintaining an NPP within established operational limits and conditions. Contents: 1. Introduction; 2. Management and organization of plant operations; 3. Shift complement and functions; 4. Shift routines and operating practices; 5. Control of equipment and plant status; 6. Operations equipment and operator aids; 7. Work control and authorization.

Guide du calcul avec les logiciels libres XCAS, Scilab, Bc, Gp, GnuPlot, Maxima, MuPAD

CERN Document Server

Connan, Guillaume

2008-01-01

Le Guide du Calcul avec les logiciels libres vous propose de maîtriser les bases de plusieurs logiciels gratuits de calcul formel et numérique, et de géométrie dynamique : XCAS, Scilab, Bc, Gp, GnuPlot, Maxima, Octave, Yacas, et également MuPAD (non libre). Ces logiciels sont multiplateformes (Windows, Mac, Linux) et s'installent rapidement. La grande originalité de cet ouvrage est de détailler pas à pas l'utilisation de plusieurs logiciels pour plusieurs types de calcul. Il propose ainsi des applications en mathématiques, en physique et en sciences de l'ingénieur (par exemple : équations différentielles utilisées en physique, traitement du son...). Il vous aidera à savoir utiliser le bon logiciel au bon moment pour résoudre le bon problème. Cet ouvrage s'adresse à toute personne voulant utiliser le calcul en mathématiques à l'aide de logiciels libres : étudiants en mathématiques ou en informatique, professeurs de lycée souhaitant utiliser ces outils dans le cadre de leur cours et jusqu'...

The Management System for Nuclear Installations. Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2017-01-01

This Safety Guide is applicable throughout the lifetime of a nuclear installation, including any subsequent period of institutional control, until there is no significant residual radiation hazard. For a nuclear installation, the lifetime includes site evaluation, design, construction, commissioning, operation and decommissioning. These stages in the lifetime of a nuclear installation may overlap. This Safety Guide may be applied to nuclear installations in the following ways: (a) To support the development, implementation, assessment and improvement of the management system of those organizations responsible for research, site evaluation, design, construction, commissioning, operation and decommissioning of a nuclear installation; (b) As an aid in the assessment by the regulatory body of the adequacy of the management system of a nuclear installation; (c) To assist an organization in specifying to a supplier, via contractual documentation, any specific element that should be included within the supplier's management system for the supply of products. This Safety Guide follows the structure of the Safety Requirements publication on The Management System for Facilities and Activities, whereby: (a) Section 2 provides recommendations on implementing the management system, including recommendations relating to safety culture, grading and documentation. (b) Section 3 provides recommendations on the responsibilities of senior management for the development and implementation of an effective management system. (c) Section 4 provides recommendations on resource management, including guidance on human resources, infrastructure and the working environment. (d) Section 5 provides recommendations on how the processes of the installation can be specified and developed, including recommendations on some generic processes of the management system. (e) Section 6 provides recommendations on the measurement, assessment and improvement of the management system of a nuclear

ASN guide project. Safety policy and management in INBs (base nuclear installations)

International Nuclear Information System (INIS)

2010-01-01

This guide presents the recommendations of the French Nuclear Safety Authority (ASN) in the field of safety policy and management (PMS) for base nuclear installations (INBs). It gives an overview and comments of some prescriptions of the so-called INB order and PMS decision. These regulatory texts define a framework for provisions any INB operator must implement to establish his safety policy, to define and implement a system which allows the safety to be maintained, the improvement of his INB safety to be permanently looked for. The following issues are addressed: operator's safety policy, identification of elements important for safety, of activities pertaining to safety, and of associated requirements, safety management organization and system, management of activities pertaining to safety, documentation and archiving

Radiation Safety in Industrial Radiography. Specific Safety Guide (Spanish Edition); Seguridad radiologica en la radiografia industrial

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-12-15

This Safety Guide provides recommendations for ensuring radiation safety in industrial radiography used in non-destructive testing. This includes industrial radiography work that utilizes X ray and gamma sources, both in shielded facilities that have effective engineering controls and in outside shielded facilities using mobile sources. Contents: 1. Introduction; 2. Duties and responsibilities; 3. Safety assessment; 4. Radiation protection programme; 5. Training and qualification; 6. Individual monitoring of workers; 7. Workplace monitoring; 8. Control of radioactive sources; 9. Safety of industrial radiography sources and exposure devices; 10. Radiography in shielded enclosures; 11. Site radiography; 12. Transport of radioactive sources; 13. Emergency preparedness and response; Appendix: IAEA categorization of radioactive sources; Annex I: Example safety assessment; Annex II: Overview of industrial radiography sources and equipment; Annex III: Examples of accidents in industrial radiography.

Probabilistic safety analysis procedures guide. Sections 1-7 and appendices. Volume 1, Revision 1

International Nuclear Information System (INIS)

Bari, R.A.; Buslik, A.J.; Cho, N.Z.

1985-08-01

A procedures guide for the performance of probabilistic safety assessment has been prepared for interim use in the Nuclear Regulatory Commission programs. It will be revised as comments are received, and as experience is gained from its use. The probabilistic safety assessment studies performed are intended to produce probabilistic predictive models that can be used and extended by the utilities and by NRC to sharpen the focus of inquiries into a range of issues affecting reactor safety. This first volume of the guide describes the determination of the probability (per year) of core damage resulting from accident initiators internal to the plant (i.e., intrinsic to plant operation) and from loss of off-site electric power. The scope includes human reliability analysis, a determination of the importance of various core damage accident sequences, and an explicit treatment and display of uncertainties for key accident sequences. The second volume deals with the treatment of the so-called external events including seismic disturbances, fires, floods, etc. Ultimately, the guide will be augmented to include the plant-specific analysis of in-plant processes (i.e., containment performance). This guide provides the structure of a probabilistic safety study to be performed, and indicates what products of the study are valuable for regulatory decision making. For internal events, methodology is treated in the guide only to the extent necessary to indicate the range of methods which is acceptable; ample reference is given to alternative methodologies which may be utilized in the performance of the study. For external events, more explicit guidance is given

Review on conformance of JMTR reactor facility to safety design examination guides for water-cooled reactors for test and research

International Nuclear Information System (INIS)

Ide, Hiroshi; Naka, Michihiro; Sakuta, Yoshiyuki; Hori, Naohiko; Matsui, Yoshinori; Miyazawa, Masataka

2009-03-01

The safety design examination guides for water-cooled reactors for test and research are formulated as fundamental judgements on the basic design validity for licensing from a viewpoint of the safety. Taking the refurbishment opportunity of the JMTR, the conformance of the JMTR reactor facility to current safety design examination guides was reviewed with licensing documents, annexes and related documents. As a result, it was found that licensing documents fully satisfied the requirements of the current guides. Moreover, it was found that the JMTR reactor facility itself also satisfied the guides requirements as well as the safety performance, since the facility with safety function such as structure, systems, devices had been installed based on the licensing documents under the permission by the regulation authority. Important devices for safety have been produced under authorization of regulating authority. Therefore, it was confirmed that the licensing was conformed to guides, and that the JMTR has enough performance. (author)

Forklift safety a practical guide to preventing powered industrial truck incidents and injuries

CERN Document Server

Swartz, George

1999-01-01

Written for the more than 1.5 million powered industrial truck operators and supervisors in general industry, as well as those in the construction and marine industries, this Second Edition provides an updated guide to training operators in safety and complying with OSHA's 1999 forklift standard. This edition of Forklift Safety includes a new chapter devoted to the new OSHA 1910.178 standard and new information regarding dock safety, narrow aisle trucks, off-dock incidents, tip-over safety, pallet safety, and carbon monoxide.

Planning and Preparing for Emergency Response to Transport Accidents Involving Radioactive Material. Safety Guide

International Nuclear Information System (INIS)

2009-01-01

This Safety Guide provides guidance on various aspects of emergency planning and preparedness for dealing effectively and safely with transport accidents involving radioactive material, including the assignment of responsibilities. It reflects the requirements specified in Safety Standards Series No. TS-R-1, Regulations for the Safe Transport of Radioactive Material, and those of Safety Series No. 115, International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. Contents: 1. Introduction; 2. Framework for planning and preparing for response to accidents in the transport of radioactive material; 3. Responsibilities for planning and preparing for response to accidents in the transport of radioactive material; 4. Planning for response to accidents in the transport of radioactive material; 5. Preparing for response to accidents in the transport of radioactive material; Appendix I: Features of the transport regulations influencing emergency response to transport accidents; Appendix II: Preliminary emergency response reference matrix; Appendix III: Guide to suitable instrumentation; Appendix IV: Overview of emergency management for a transport accident involving radioactive material; Appendix V: Examples of response to transport accidents; Appendix VI: Example equipment kit for a radiation protection team; Annex I: Example of guidance on emergency response to carriers; Annex II: Emergency response guide.

IAEA activities to prepare safety codes and guides for thermal neutron nuclear power plants

International Nuclear Information System (INIS)

Iansiti, E.

1977-01-01

In accordance with the programme presented to, and endorsed by, the eighteenth General Conference in September 1974, the IAEA is now developing a complete set of safety codes and guides that will represent recommendations for the safety of thermal neutron power plants. The safety codes outline the minimum requirements for achieving this safety, and the safety guides set forth the criteria, procedures and methods to implement the safety codes. The whole programme is directed towards the five areas of Governmental Organization, Siting, Design, Operation, and Quality Assurance. One Scientific Secretary from the Agency Secretariat is responsible for each of these areas and a Co-ordinator takes care of common problems. For the development of each of these documents a working group of a few world experts is first convened which prepare a preliminary draft. This draft is then reviewed by a larger, international Technical Review Committee (one for each of the five areas) and a subsequent review by the Senior Advisory Group - with representatives from 20 states - ensures that the document is well coordinated within the programme. At this stage, it is sent to Member States for comments. The Technical Review Committee concerned is reconvened to integrate these comments into the document, and, after a final review by the Senior Advisory Group, the document is ready for transmission to the Director General of the Agency for endorsement and publication. A preliminary to this procedure is the collation by the Secretariat of large amounts of information submitted by Member States so that the first draft is really based on a very complete knowledge of what is done in each area all over the world. This collation frequently reveals differences in approach which are not random but due, rather, to the local conditions and the types of reactors. These differences must be harmonized in the documents produced without detracting from the effectiveness of the code or guide. The whole

Un guide colonial. Le Guide du Voyageur au Congo belge et au Ruanda-Urundi A colonial guidebook. Travel guide to Belgian Congo and Ruanda-Urundi

Directory of Open Access Journals (Sweden)

Henri Nicolaï

2013-03-01

Full Text Available Le Guide, qui a connu cinq éditions pendant les dix dernières années du Congo belge, est un archétype du guide colonial. L’article rappelle d’abord la naissance du tourisme en Afrique centrale et ses caractéristiques. Fasciné longtemps par les mythes des Monts de la Lune et des sources du Nil, le tourisme congolais est, au départ, essentiellement élitiste, orienté surtout vers la grande chasse sportive. Gorilles de montagne, ascensions du Ruwenzori, danseurs Tutsi, Parc National Albert, pêcheurs wagenia deviennent les icônes d’un tourisme attiré en ordre principal par le Kivu, les Grands Lacs, Stanleyville et secondairement le Katanga. Le premier guide, édité par Vicicongo, en 1934, s’intitule d’ailleurs Congo-Nil. Tous ces mythes et ces décors se retrouvent dans quelques grands films américains d’aventure du début des années 50.L’article décrit ensuite la genèse du Guide, ses caractéristiques générales, son plan, son contenu. Beaucoup d’informations générales, pas de véritables circuits mais plutôt des itinéraires routiers. Produit par les services officiels d’information de la Colonie, le Guide a, parmi ses objectifs, de montrer la persistance et les résultats de l’action civilisatrice de la Belgique. Il affirme que le Congo n’est pas un pays d’art ni d’histoire et accorde donc une part prépondérante au milieu naturel. Il fournit une image tronquée de son histoire et exprime sur ses habitants les préjugés de l’époque.L’article se termine par quelques réflexions sur les tentatives d’un reporter d’une chaîne de télévision et d’un photographe d’utiliser le Guide de 1958 pour parcourir le pays un demi-siècle plus tard.The Travel Guide to Belgian Congo and Ruanda-Urundi, of which five editions were released during the last ten years of Belgian Congo, is an archetypal colonial guide.The paper first highlights the emergence and the features of tourism in Central Africa

Australian Radiation Protection and Nuclear Safety Act 1998. Guide to the Australian radiation protection and nuclear safety licensing framework. 1. ed.

International Nuclear Information System (INIS)

1999-03-01

The purpose of this guide is to provide information to Commonwealth entities who may require a license under the Australian Radiation Protection and Nuclear Safety (ARPANS) Act 1998 to enable them to posses, have control of, use, operate or dispose of radiation sources. The guide describes to which agencies and what activities require licensing. It also addresses general administrative and legal matters such as appeal procedures, ongoing licensing requirements, monitoring and compliance. Applicants are advised to consult the Australian Radiation Protection and Nuclear Safety Act 1998 and accompanying Regulations when submitting applications

Australian Radiation Protection and Nuclear Safety Act 1998. Guide to the Australian radiation protection and nuclear safety licensing framework; 1. ed

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-03-01

The purpose of this guide is to provide information to Commonwealth entities who may require a license under the Australian Radiation Protection and Nuclear Safety (ARPANS) Act 1998 to enable them to posses, have control of, use, operate or dispose of radiation sources. The guide describes to which agencies and what activities require licensing. It also addresses general administrative and legal matters such as appeal procedures, ongoing licensing requirements, monitoring and compliance. Applicants are advised to consult the Australian Radiation Protection and Nuclear Safety Act 1998 and accompanying Regulations when submitting applications

Tornadoes: Nature's Most Violent Storms. A Preparedness Guide Including Safety Information for Schools.

Science.gov (United States)

American National Red Cross, Washington, DC.

This preparedness guide explains and describes tornadoes, and includes safety information for schools. A tornado is defined as a violently rotating column of air extending from a thunderstorm to the ground. The guide explains the cause of tornadoes, provides diagrams of how they form, describes variations of tornadoes, and classifies tornadoes by…

Criticality guide. I - Introduction to criticality. II - Practical rules. III - Curves; Guide de criticite. I - Introduction a la criticite. II - Regles pratiques. III - Courbes

Energy Technology Data Exchange (ETDEWEB)

NONE

1967-07-01

Somme elements of neutronics are presented in a simple and often intuitive way; the 'K infinite' and 'K effective' formulae are derived and discussed. The limiting solid angle method is explained and some simple formulae proposed for evaluating the interaction between 'fissile units'. The general principles used in studying the safety of nuclear installations using fissile matter are given. Practical rules, critical mass and critical geometry curves as well as all the numerical values required for normal criticality calculations are given for plutonium and uranium at various degrees of enrichment. This guide is not intended to produce experts in criticality and cannot replace the advice which can be given by specialists of a science which is still expanding rapidly. It should however simplify the task of these specialists by familiarising with these problems both the engineers and scientists in charge of the design of installations using fissile matter, and the persons in charge of their operation. (author) [French] Des elements de neutronique sont exposes d'une fapon simple et souvent intuitive les formules du 'K infini' et du 'K effectif' sont etablies et commentees. La 'methode de l'angle solide limite' est expliquee et des formules simples proposees pour evaluer l'interaction entre des 'unites fissiles'. Les principes generaux utilises dans les etudes de surete nucleaire d'installation, mettant en ceuvre des matieres fissiles, sont donnes. Des regles pratiques, des courbes de masse et geometrie critiques ainsi que toutes les valeurs numeriques necessaires aux calculs usuels de criticite sont fournies pour du plutonium et de l'uranium a divers enrichissements. Ce guide n'a pas la pretention de former des experts en criticite et ne doit pas dispenser de s'entourer de l'avis de specialistes dans une science encore en pleine evolution. II doit simplement faciliter la tache de ceux-ci, en familiarisant avec ces problemes les ingenieurs charges de la conception des

Predisposal Management of Low and Intermediate Level Radioactive Waste. Safety Guide

International Nuclear Information System (INIS)

2009-01-01

The objective of this Safety Guide is to provide regulatory bodies and the operators that generate and manage radioactive waste with recommendations on how to meet the principles and requirements established for the predisposal management of low and intermediate level waste. Contents: 1. Introduction; 2. Protection of human health and the environment; 3. Roles and responsibilities; 4. General safety considerations; 5. Safety features for the predisposal management of LILW; 6. Record keeping and reporting; 7. Safety assessment; 8. Quality assurance; Annex I: Nature and sources of LILW from nuclear facilities; Annex II: Development of specifications for waste packages; Annex III: Site conditions, processes and events for consideration in a safety assessment (external natural phenomena); Annex IV: Site conditions, processes and events for consideration in a safety assessment (external human induced phenomena); Annex V: Postulated initiating events for consideration in a safety assessment (internal phenomena).

Regulatory inspection of nuclear facilities and enforcement by the regulatory body. Safety guide

International Nuclear Information System (INIS)

2002-01-01

The purpose of this Safety Guide is to provide recommendations for regulatory bodies on the inspection of nuclear facilities, regulatory enforcement and related matters. The objective is to provide the regulatory body with a high level of confidence that operators have the processes in place to ensure compliance and that they do comply with legal requirements, including meeting the safety objectives and requirements of the regulatory body. However, in the event of non-compliance, the regulatory body should take appropriate enforcement action. This Safety Guide covers regulatory inspection and enforcement in relation to nuclear facilities such as: enrichment and fuel manufacturing plants; nuclear power plants; other reactors such as research reactors and critical assemblies; spent fuel reprocessing plants; and facilities for radioactive waste management, such as treatment, storage and disposal facilities. This Safety Guide also covers issues relating to the decommissioning of nuclear facilities, the closure of waste disposal facilities and site rehabilitation. Section 2 sets out the objectives of regulatory inspection and enforcement. Section 3 covers the management of regulatory inspections. Section 4 covers the performance of regulatory inspections, including internal guidance, planning and preparation, methods of inspection and reports of inspections. Section 5 deals with regulatory enforcement actions. Section 6 covers the assessment of regulatory inspections and enforcement activities. The Appendix provides further details on inspection areas for nuclear facilities

A SIL quantification approach based on an operating situation model for safety evaluation in complex guided transportation systems

International Nuclear Information System (INIS)

Beugin, J.; Renaux, D.; Cauffriez, L.

2007-01-01

Safety analysis in guided transportation systems is essential to avoid rare but potentially catastrophic accidents. This article presents a quantitative probabilistic model that integrates Safety Integrity Levels (SIL) for evaluating the safety of such systems. The standardized SIL indicator allows the safety requirements of each safety subsystem, function and/or piece of equipment to be specified, making SILs pivotal parameters in safety evaluation. However, different interpretations of SIL exist, and faced with the complexity of guided transportation systems, the current SIL allocation methods are inadequate for the task of safety assessment. To remedy these problems, the model developed in this paper seeks to verify, during the design phase of guided transportation system, whether or not the safety specifications established by the transport authorities allow the overall safety target to be attained (i.e., if the SIL allocated to the different safety functions are sufficient to ensure the required level of safety). To meet this objective, the model is based both on the operating situation concept and on Monte Carlo simulation. The former allows safety systems to be formalized and their dynamics to be analyzed in order to show the evolution of the system in time and space, and the latter make it possible to perform probabilistic calculations based on the scenario structure obtained

Preliminary standard review guide for Environmental Restoration/Decontamination and Decommissioning safety analyses

International Nuclear Information System (INIS)

Ellingson, D.R.

1993-06-01

The review guide is based on the shared experiences, approaches, and philosophies of the Environmental Restoration/Decontamination and Decommissioning (ER/D ampersand D) subgroup members. It is presented in the form of a review guide to maximize the benefit to both the safety analyses practitioner and reviewer. The guide focuses on those challenges that tend to be unique to ER/D ampersand D cleanup activities. Some of these experiences, approaches, and philosophies may find application or be beneficial to a broader spectrum of activities such as terminal cleanout or even new operations. Challenges unique to ER/D ampersand D activities include (1) consent agreements requiring activity startup on designated dates; (2) the increased uncertainty of specific hazards; and (3) the highly variable activities covered under the broad category of ER/D ampersand D. These unique challenges are in addition to the challenges encountered in all activities; e.g., new and changing requirements and multiple interpretations. The experiences in approaches, methods, and solutions to the challenges are documented from the practitioner and reviewer's perspective, thereby providing the viewpoints on why a direction was taken and the concerns expressed. Site cleanup consent agreements with predetermined dates for restoration activity startup add the dimension of imposed punitive actions for failure to meet the date. Approval of the safety analysis is a prerequisite to startup. Actions that increase expediency are (1) assuring activity safety; (2) documenting that assurance; and (3) acquiring the necessary approvals. These actions increase the timeliness of startup and decrease the potential for punitive action. Improvement in expediency has been achieved by using safety analysis techniques to provide input to the line management decision process rather than as a review of line management decisions. Expediency is also improved by sharing the safety input and resultant decisions with

Guide pour la conception des dispositifs de franchissement des barrages pour les poissons migrateurs

Directory of Open Access Journals (Sweden)

LARINIER M.

1983-10-01

Full Text Available L'auteur rappelle dans cette note les principes de base devant guider le projeteur lors de la conception des ouvrages de franchissement de barrages ou d'obstacles pour les poissons migrateurs. L'accent est mis sur l'importance de la situation et de l'attractivité de ces ouvrages. Les principes de fonctionnement et les critères de dimensionnement des différents types de passes (passes à bassins successifs, passes à ralentisseurs, écluses et ascenseurs sont évoqués. Dans la dernière partie sont recensés les éléments à prendre en compte lors de l'établissement d'un projet de passe.

External human induced events in site evaluation for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2004-01-01

The purpose of the present Safety Guide is to provide recommendations and guidance for the examination of the region considered for site evaluation for a plant in order to identity hazardous phenomena associated with human induced events initiated by sources external to the plant. In some cases it also presents preliminary guidance for deriving values of relevant parameters for the design basis. This Safety Guide is also applicable for periodic site evaluation and site evaluation following a major human induced event, and for the design and operation of the site's environmental monitoring system. Site evaluation includes site characterization. Consideration of external events that could lead to a degradation of the safety features of the plant and cause a release of radioactive material from the plant and/or affect the dispersion of such material in the environment. And consideration of population issues and access issues significant to safety (such as the feasibility of evacuation, the population distribution and the location of resources). The process of site evaluation continues throughout the lifetime of the facility, from siting to design, construction, operation and decommissioning. The external human induced events considered in this Safety Guide are all of accidental origin. Considerations relating to the physical protection of the plant against wilful actions by third parties are outside its scope. However, the methods described herein may also have some application for the purposes of such physical protection. The present Safety Guide may also be used for events that may originate within the boundaries of the site, but from sources which are not directly involved in the operational states of the nuclear power plant units, such as fuel depots or areas for the storage of hazardous materials for the construction of other facilities at the same site. Special consideration should be given to the hazardous material handled during the construction, operation and

Predisposal Management of Radioactive Waste from Nuclear Fuel Cycle Facilities. Specific Safety Guide

International Nuclear Information System (INIS)

2016-01-01

This Safety Guide provides guidance on the predisposal management of all types of radioactive waste (including spent nuclear fuel declared as waste and high level waste) generated at nuclear fuel cycle facilities. These waste management facilities may be located within larger facilities or may be separate, dedicated waste management facilities (including centralized waste management facilities). The Safety Guide covers all stages in the lifetime of these facilities, including their siting, design, construction, commissioning, operation, and shutdown and decommissioning. It covers all steps carried out in the management of radioactive waste following its generation up to (but not including) disposal, including its processing (pretreatment, treatment and conditioning). Radioactive waste generated both during normal operation and in accident conditions is considered

La gastronomie dans les guides de voyage : de la richesse industrielle au patrimoine culturel, France XIXe-début XXe siècle

Directory of Open Access Journals (Sweden)

Julia Csergo

2011-06-01

Full Text Available Les guides de voyage constituent une source majeure pour une histoire de l’alimentation. Ils nous éclairent sur les temps et les lieux des productions et des consommations alimentaires, sur la construction des images des territoires gourmands et des stéréotypes culinaires. Au-delà, ils constituent, surtout à partir du XIXe siècle qui voit la naissance concomitante de la notion de « gastronomie » (pratique sociale qui s’organise autour de savoir et de savoir-faire, de rites, de gestes et de discours et de celle de « patrimoine » (monument historique, un des principaux médias par lequel appréhender le processus de culturalisation et de patrimonialisation de la gastronomie qui devient, pour le touriste, une forme de consommation culturelle, au même titre que celle des sites et monuments.Travel guides constitute a major source for an history of food. They shed light on times and places of the food productions and consumptions, on the building of the « gourmands » territories and of culinary stereotypes. Moreover, they constitute, especially since the 19h century, in which emerge the notions of “gastronomy” (a social practice organized around knowledge and know-how, rituals, gestures and discourses and “patrimony” (historic building, one of the main mass media relating the process of gastronomy becoming a cultural legacy becoming, for the tourist, a way of cultural consumption, just like sites and monuments.

Inspection and enforcement by the regulatory body for nuclear power plants. A safety guide. A publication within the NUSS programme

International Nuclear Information System (INIS)

1996-01-01

The purpose of this Safety Guide is to provide guidance on fulfilling the requirements for inspection and enforcement by the regulatory body, as set out in the Code on the Safety of Nuclear Power Plants; Governmental Organization. This Safety Guide deals with the responsibilities of the regulatory body, the organization of inspection programmes, the inspection resources of the regulatory body, methods of inspection, requirements on the applicant/licensee in regard to regulatory inspection, inspection reports, and regulatory action and enforcement. It is recognized that many of the provisions of this Safety Guide may be applicable to the regulations of other nuclear facilities and related activities including research reactors, fuel processing and manufacturing plants, irradiated fuel processing plants and radioactive waste management facilities. This Safety Guide does not deal specifically with the functions of a regulatory body responsible for such matters; however, the guidance presented here may be applied as appropriate to these activities. 11 refs, 1 fig

Les aciers inoxydables dans les fixations

CERN Document Server

CETIM

2010-01-01

Cet ouvrage, qui fait la synthèse de plusieurs travaux menés par le Cetim, propose une vue d'ensemble sur les aciers inoxydables utilisés pour les fixations. Au sommaire : les normes EN, ISO et ATSM qui s'y rapportent , les désignations symboliques , les nuances et caractéristiques mécaniques , les différentes formes de corrosion, les méthodes pour les détecter , les règles du métier , les mises en oeuvre. L'ouvrage comprend plusieurs fiches matériaux et des tableaux qui présentent les équivalences entre les désignations.

The guide to sustainable energy technologies for schools; Un guide pour les technologies energetiques durables dans les ecoles

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-07-01

There are significant attractions for municipalities to opt for sustainable solutions which involve energy efficient technologies and measures. This is the challenging background which led to the production the Guide to Sustainable Energy Technologies for Schools. This guide is a decision-making tool intended for European municipalities and school managers. Its aim is to: assist them in choosing between the energy technologies that will be used in school building or retrofitting projects and provide them with a framework for measuring and comparing different aspects of energy performance that can be used to convince decision-makers to select sustainable energy technologies and measures. The guide is composed of three parts: an illustrative list of sustainable energy technologies, an introduction to energy performance indicators and fifteen case studies describing practical sustainable energy solutions applied to schools in seven European countries. (A.L.B.)

Environmental and Source Monitoring for Purposes of Radiation Protection. Safety Guide (Spanish ed.)

International Nuclear Information System (INIS)

2010-01-01

The purpose of this Safety Guide is to provide international guidance, coherent with contemporary radiation protection principles and IAEA safety requirements, on the strategy of monitoring in relation to: (a) control of radionuclide discharges under practice conditions, and (b) intervention, such as in cases of nuclear or radiological emergencies or past contamination of areas with long lived radionuclides. Three categories of monitoring are discussed: monitoring at the source of the discharge (source monitoring), monitoring in the environment (environmental monitoring) and monitoring of individual exposure in emergencies (individual monitoring). The Safety Guide also provides general guidance on assessment of the doses to critical groups of the population due to the presence of radioactive materials or radiation fields in the environment both from routine operation of nuclear and other related facilities (practice) and from nuclear or radiological emergencies and past contamination of areas with long lived radionuclides (intervention). The dose assessments are based on the results of source monitoring, environmental monitoring, individual monitoring or their combinations. This Safety Guide is primarily intended for use by national regulatory bodies and other agencies involved in national systems of radiation monitoring, as well as by operators of nuclear installations and other facilities where natural or human made radionuclides are treated and monitored. Contents: 1. Introduction; 2. Meeting regulatory requirements for monitoring in practices and interventions; 3. Responsibilities for monitoring; 4. Generic aspects of monitoring programmes; 5. Programmes for monitoring in practices and interventions; 6. Technical conditions for monitoring procedures; 7. Considerations in dose assessment; 8. Interpretation of monitoring results; 9. Quality assurance; 10. Recording of results; 11. Education and training; Glossary.

Safety codes and guides for nuclear power plants

International Nuclear Information System (INIS)

Iansiti, E.

1976-01-01

The Codes of Practice and Safety Guides that are being developed by the International Atomic Energy Agency are divided in five topical areas: Governmental Organization, Siting, Design, Operation and Quality Assurance. In each area, a scientific secretary is responsible for developing the documents and five Technical Review Committees composed of 10 to 12 experts from various Members Countries revise the drafts at different stages. A Senior Advisory Group supervises the entire programme and revises the document. A scientific co-ordinator is responsible for the co-ordination within the programme with other sections of the IAEA, and with other international organizations. In preparing a document, information on the practice adopted by Member States is collected, a group of experts is convened for preparing a preliminary draft on the basis of this material and the draft is then reviewed by the appropriate Technical Review Committee. The document is translated into various languages, reviewed by the Senior Advisory Group and sent to Member States for comments. After the comments of Member States have been received, the Technical Review Committee and then the Senior Advisory Group are convened again for the final revision of the document. Some 25 drafts, are in different stages of development. The preparation of a document in its final form takes about two years. The programme started in 1975 and to date most of the safety codes and a few safety guides have been sent to Member States for comments. These documents will have gone through the entire development procedure by early 1977. The Senior Advisory Groups and the Technical Review Committees meet on the average four times a year for a week at a time. Until now these meetings have been mainly concerned with the development of new documents or with that part of the procedure which precedes the transmission of the draft to Member States for comments. The next series of meetings will deal with the revisions needed to

Dispersion of radioactive material in air and water and consideration of population distribution in site evaluation for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2004-01-01

The IAEA issues Safety Requirements and Safety Guides pertaining to nuclear power plants and activities in the field of nuclear energy, on the basis of its Safety Fundamentals publication on The Safety of Nuclear Installations. The present Safety Guide, which supplements the Code on the Safety of Nuclear Power Plants: Siting, concerns the effects of a nuclear power plant on the surrounding region and the consideration of population distribution in the siting of a plant. This Safety Guide makes recommendations on how to meet the requirements of the Code on the Safety of Nuclear Power Plants: Siting, on the basis of knowledge of the mechanisms for the dispersion of effluents discharged into the atmosphere and into surface water and groundwater. Relevant site characteristics and safety considerations are discussed. Population distribution, the projected population growth rate, particular geographical features, the capabilities of local transport networks and communications networks, industry and agriculture in the region, and recreational and institutional activities in the region should be considered in assessing the feasibility of developing an emergency response plan. In the selection of a site for a facility using radioactive material, such as a nuclear power plant, account should be taken of any local features that might be affected by the facility and of the feasibility of off-site intervention, including emergency response and protective actions. This is in addition to the evaluation of any features of the site itself that might affect the safety of the facility. This Safety Guide recommends methods for the assessment of regional and local characteristics. This Safety Guide supersedes four earlier IAEA Safety Guides, namely: Atmospheric Dispersion in Nuclear Power Plant Siting (Safety Series No. 50-SG-S3 (1980)). Site Selection and Evaluation for Nuclear Power Plants with Respect to Population Distribution (Safety Series No. 50-SG-S4 (1980)). Hydrological

Dispersion of radioactive material in air and water and consideration of population distribution in site evaluation for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2002-01-01

The IAEA issues Safety Requirements and Safety Guides pertaining to nuclear power plants and activities in the field of nuclear energy, on the basis of its Safety Fundamentals publication on The Safety of Nuclear Installations. The present Safety Guide, which supplements the Code on the Safety of Nuclear Power Plants: Siting, concerns the effects of a nuclear power plant on the surrounding region and the consideration of population distribution in the siting of a plant. This Safety Guide makes recommendations on how to meet the requirements of the Code on the Safety of Nuclear Power Plants: Siting, on the basis of knowledge of the mechanisms for the dispersion of effluents discharged into the atmosphere and into surface water and groundwater. Relevant site characteristics and safety considerations are discussed. Population distribution, the projected population growth rate, particular geographical features, the capabilities of local transport networks and communications networks, industry and agriculture in the region, and recreational and institutional activities in the region should be considered in assessing the feasibility of developing an emergency response plan. In the selection of a site for a facility using radioactive material, such as a nuclear power plant, account should be taken of any local features that might be affected by the facility and of the feasibility of off-site intervention, including emergency response and protective actions. This is in addition to the evaluation of any features of the site itself that might affect the safety of the facility. This Safety Guide recommends methods for the assessment of regional and local characteristics. This Safety Guide supersedes four earlier IAEA Safety Guides, namely: Atmospheric Dispersion in Nuclear Power Plant Siting (Safety Series No. 50-SG-S3 (1980)); Site Selection and Evaluation for Nuclear Power Plants with Respect to Population Distribution (Safety Series No. 50-SG-S4 (1980)); Hydrological

La puissance prescriptive des guides à Paris The prescriptive power of tour guides in Paris. Standardizing elements of tourism ?

Directory of Open Access Journals (Sweden)

Gwendal Simon

2008-10-01

Full Text Available Les « guide-interprètes » constituent des médiateurs entre les touristes et les espaces. Incarnant une présence physique en mesure d’aider les touristes en les informant sur la ville, ils opèrent comme prescripteurs de choses à voir et à faire. S’ils officient très diversement selon les touristes qu’ils accompagnent, ils exercent toujours leur pratique dans une logique de production de discours sur la ville. À Paris, la dimension muséale et patrimoniale constitue depuis longtemps le socle de l’attractivité touristique, qui continue de capitaliser sur des imaginaires et des pratiques liés à la grande ville d’Art et d’Histoire. Face à la constitution de ce référentiel dominant qui opère comme une force d’ « imposition », les guide-interprètes tentent néanmoins de décentrer le regard par des prescriptions délestées des symboles. C’est cette « tension » entre cet ensemble de références touristiques « à voir » et le souci de montrer la ville dans sa pluralité que nous analysons. Ces éléments nourrissent la réflexion actuelle sur les formes polarisées du tourisme à Paris et l’importance de la production de référents urbains plus contemporains que promeut la municipalité.Tour guides are mediators between tourists and spaces. As they embody a physical presence helping tourists and informing them about the city, they also act as prescribers, laying down what is supposed to be seen and to be done. If their recommendations depend on the tourists they travel with, they always mean to produce a discourse on the city. Paris’ museums and heritage have long since been two cornerstones of her enduring appeal. Confronted with this phenomenon, which tends to standardize the way of visiting a city, tour guides try to free their guidelines of symbolic references. This contribution focuses on the tension between must-see tourist references and the desire to show the city in all its diversity. These

Abolir les obstacles que constituent les frais de santé : les ...

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

10 juin 2016 ... Abolir les obstacles que constituent les frais de santé : les ... Le financement des services de santé repose sur un système de ... Dans les années 1980, conformément aux recommandations d'organismes internationaux, ...

Les jeux de hasard chez les enfants et les adolescents

Science.gov (United States)

Gupta, Rina; Pinzon, Jorge L

2012-01-01

RÉSUMÉ Même si, au Canada, les mineurs n’ont pas le droit de jouer à des jeux de hasard légalisés, les adolescents participent souvent à des jeux de hasard soit légalisés (produits de loterie, casino, terminaux de jeux vidéo), soit autonomes (jeux de cartes, paris sportifs, dés) à la maison et en milieu scolaire. Chez les adultes, le taux de prévalence de dépendance aux jeux de hasard au cours de la vie se situe entre 1 % et 2 %. D’après les données existantes, la prévalence chez les adolescents serait de deux à quatre fois plus élevée. On ne sait pas grand-chose des facteurs de risque d’apparition et de perpétuation d’une dépendance pathologique aux jeux de hasard. Le présent document de principes vise à informer les pédiatres, les médecins de famille et les autres professionnels de la santé des connaissances émergentes sur les jeux de hasard pendant l’enfance et l’adolescence et du risque de conséquences graves qui s’y rattachent. On y exhorte également les gouvernements fédéral, provinciaux et territoriaux à inclure cette question dans leur programme et à tenir compte des facteurs sociopolitiques associés aux jeux de hasard.

Radiological protection for medical exposure to ionizing radiation. Safety guide

International Nuclear Information System (INIS)

2002-01-01

radiotherapy owing to an ageing population. In addition, further growth in medical radiology can be expected in developing States, where at present facilities and services are often lacking. The risks associated with these expected increases in medical exposures should be outweighed by the benefits. For the purposes of radiation protection, ionizing radiation exposures are divided into three types: Medical exposure, which is mainly the exposure of patients as part of their diagnosis or treatment (see below); Occupational exposure, which is the exposure of workers incurred in the course of their work, with some specific exclusions; and Public exposure, which comprises all other exposures of members of the public that are susceptible to human control. Medical exposure is defined in the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (BSS, the Standards) as: 'Exposure incurred by patients as part of their own medical or dental diagnosis or treatment; by persons, other than those occupationally exposed, knowingly while voluntarily helping in the support and comfort of patients; and by volunteers in a programme of biomedical research involving their exposure.' This Safety Guide covers all of the medical exposures defined above, with emphasis on the radiological protection of patients, but does not cover exposures of workers or the public derived from the application of medical radiation sources. Guidance relating to these exposures can be found in the Safety Guide on Occupational Radiation Protection. In addition to the IAEA, several intergovernmental and international organizations, among them the European Commission, the International Commission on Radiological Protection (ICRP), the Pan American Health Organization (PAHO) and the World Health Organization (WHO), have already published numerous recommendations, guides and codes of practice relevant to this subject area. National authorities should therefore

Radiological protection for medical exposure to ionizing radiation. Safety guide

International Nuclear Information System (INIS)

2005-01-01

radiotherapy owing to an ageing population. In addition, further growth in medical radiology can be expected in developing States, where at present facilities and services are often lacking. The risks associated with these expected increases in medical exposures should be outweighed by the benefits. For the purposes of radiation protection, ionizing radiation exposures are divided into three types: Medical exposure, which is mainly the exposure of patients as part of their diagnosis or treatment (see below). Occupational exposure, which is the exposure of workers incurred in the course of their work, with some specific exclusions. And Public exposure, which comprises all other exposures of members of the public that are susceptible to human control. Medical exposure is defined in the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (BSS, the Standards) as: 'Exposure incurred by patients as part of their own medical or dental diagnosis or treatment. By persons, other than those occupationally exposed, knowingly while voluntarily helping in the support and comfort of patients. And by volunteers in a programme of biomedical research involving their exposure.' This Safety Guide covers all of the medical exposures defined above, with emphasis on the radiological protection of patients, but does not cover exposures of workers or the public derived from the application of medical radiation sources. Guidance relating to these exposures can be found in the Safety Guide on Occupational Radiation Protection. In addition to the IAEA, several intergovernmental and international organizations, among them the European Commission, the International Commission on Radiological Protection (ICRP), the Pan American Health Organization (PAHO) and the World Health Organization (WHO), have already published numerous recommendations, guides and codes of practice relevant to this subject area. National authorities should therefore

Radiation Protection and Radioactive Waste Management in the Operation of Nuclear Power Plants. Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2010-01-01

The purpose of this Safety Guide is to provide recommendations to the regulatory body, focused on the operational aspects of radiation protection and radioactive waste management in nuclear power plants, and on how to ensure the fulfilment of the requirements established in the relevant Safety Requirements publications. It will also be useful for senior managers in licensee or contractor organizations who are responsible for establishing and managing programmes for radiation protection and for the management of radioactive waste. This Safety Guide gives general recommendations for the development of radiation protection programmes at nuclear power plants. The issues are then elaborated by defining the main elements of a radiation protection programme. Particular attention is paid to area classification, workplace monitoring and supervision, application of the principle of optimization of protection (also termed the 'as low as reasonably achievable' (ALARA) principle), and facilities and equipment. This Safety Guide covers all the safety related aspects of a programme for the management of radioactive waste at a nuclear power plant. Emphasis is placed on the minimization of waste in terms of both activity and volume. The various steps in predisposal waste management are covered, namely processing (pretreatment, treatment and conditioning), storage and transport. Releases of effluents, the application of authorized limits and reference levels are discussed, together with the main elements of an environmental monitoring programme

The SAFER guides: empowering organizations to improve the safety and effectiveness of electronic health records.

Science.gov (United States)

Sittig, Dean F; Ash, Joan S; Singh, Hardeep

2014-05-01

Electronic health records (EHRs) have potential to improve quality and safety of healthcare. However, EHR users have experienced safety concerns from EHR design and usability features that are not optimally adapted for the complex work flow of real-world practice. Few strategies exist to address unintended consequences from implementation of EHRs and other health information technologies. We propose that organizations equipped with EHRs should consider the strategy of "proactive risk assessment" of their EHR-enabled healthcare system to identify and address EHR-related safety concerns. In this paper, we describe the conceptual underpinning of an EHR-related self-assessment strategy to provide institutions a foundation upon which they could build their safety efforts. With support from the Office of the National Coordinator for Health Information Technology (ONC), we used a rigorous, iterative process to develop a set of 9 self-assessment tools to optimize the safety and safe use of EHRs. These tools, referred to as the Safety Assurance Factors for EHR Resilience (SAFER) guides, could be used to self-assess safety and effectiveness of EHR implementations, identify specific areas of vulnerability, and create solutions and culture change to mitigate risks. A variety of audiences could conduct these assessments, including frontline clinicians or care teams in different practices, or clinical, quality, or administrative leaders within larger institutions. The guides use a multifaceted systems-based approach to assess risk and empower organizations to work with internal or external stakeholders (eg, EHR developers) on optimizing EHR functionality and using EHRs to drive improvements in the quality and safety of healthcare.

Management of Radioactive Waste from the Mining and Milling of Ores. Safety Guide (Spanish ed.)

International Nuclear Information System (INIS)

2010-01-01

This Safety Guide provides recommendations and guidance on the safe management of radioactive waste resulting from the mining and milling of ores, with the purpose of protecting workers, the public and the environment from the consequences of these activities. It supplements Safety Standards Series No. WS-R-1, Near Surface Disposal of Radioactive Waste. Contents: 1. Introduction; 2. Administrative, legal and regulatory framework; 3. Protection of human health and the environment; 4. Strategy for waste management; 5. Safety considerations in different phases of operations; 6. Safety assessment; 7. Quality assurance; 8. Monitoring and surveillance; 9. Institutional control for the post-closure phase.

Evaluation of safety assessment methodologies in Rocky Flats Risk Assessment Guide (1985) and Building 707 Final Safety Analysis Report (1987)

International Nuclear Information System (INIS)

Walsh, B.; Fisher, C.; Zigler, G.; Clark, R.A.

1990-01-01

FSARs. Rockwell International, as operating contractor at the Rocky Flats plant, conducted a safety analysis program during the 1980s. That effort resulted in Final Safety Analysis Reports (FSARs) for several buildings, one of them being the Building 707 Final Safety Analysis Report, June 87 (707FSAR) and a Plant Safety Analysis Report. Rocky Flats Risk Assessment Guide, March 1985 (RFRAG85) documents the methodologies that were used for those FSARs. Resources available for preparation of those Rocky Flats FSARs were very limited. After addressing the more pressing safety issues, some of which are described below, the present contractor (EG ampersand G) intends to conduct a program of upgrading the FSARs. This report presents the results of a review of the methodologies described in RFRAG85 and 707FSAR and contains suggestions that might be incorporated into the methodology for the FSAR upgrade effort

Communication et participation communautaire : Guide pratique de ...

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

Ce guide est destiné aux personnes qui travaillent dans le secteur de la recherche et du développement. Il présente les concepts de la communication participative pour le développement, traite des méthodes de communication bilatérale efficaces, et présente une méthodologie pour planifier, élaborer et évaluer les ...

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

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

1 janv. 2006 ... Environmental Regulation and Food Safety intéressera les artisans des politiques et les ONG , les chercheurs et les spécialistes de l'économie ... This funding will help strengthen the Science, Technology and Innovation Policy Research Organization's (STIPRO) role as a credible public policy institution in ...

Lessons Learned from Process Safety Management: A Practical Guide to Defence in Depth

Energy Technology Data Exchange (ETDEWEB)

Langerman, N., E-mail: neal@chemical-safety.com [Advanced Chemical Safety, Inc., San Diego (United States)

2014-10-15

Full text: Beginning with the experiences of Alfred Nobel, the chemical enterprise has learned from failures and implemented layers of protection to prevent unwanted incidents. Nobel developed dynamite as a more stable alternative to nitroglycerin, a process we would today call “inherently safer technology”. In recent years, the USA has issued regulations requiring formal “risk management plans” to identify and mitigate production risks. The USA set up the “Chemical Safety and Hazard Investigation Board” as an independent investigator of serious chemical enterprise incidents with a mission to issue recommendations aimed at preventing repeated incidents based on lessons learned. Following a particularly violent explosion in Texas in 1989, the US Occupational Safety and Health Administration issued the “Process Safety Management” (PSM) rule. PSM is a singular guide to defence in depth for preventing large-scale production incidents. The formalism is equally applicable to the chemical enterprise and the nuclear installation enterprise. This presentation will discuss the key elements of PSM and offer suggestions on using PSM as a guide to developing multiple layers of protection. The methods of PSM are applicable to Nuclear Generating Stations, research reactors, fuel reprocessing plants and fissile material storage and handling. Examples from both the chemical and nuclear enterprises will be used to illustrate key points. (author)

L'électronique pour les débutants qui sèchent les cours mais soudent sans se brûler les doigts

CERN Document Server

Mallard, Rémy

2012-01-01

Par où commencer pour débuter en électronique ? Vais-je m'égarer en explorant l'internet ? Il regorge de schémas, mais sont-ils fiables ? Me faut-il un livre avec des montages simples ou plutôt un livre sur les composants ? Après trente ans de pratique, l'auteur de ce livre, resté l'éternel débutant qui réalisait lui-même son premier montage dès l'âge de dix ans, partage ici sa soif toujours vive d'apprendre. Fin pédagogue, il guide les débutants et répond aux questions que trop de livres laissent en suspens : "Quel type de fer à souder acheter ?"... "Un multimètre à 5 € peut-il suffire ?"... "Un oscilloscope est-il indispensable ?"... "Peut-on installer son montage dans une boîte à cigares ?"... Rémy Mallard démystifie l'électronique en n'utilisant que ce qu'il vous faut de théorie pour aborder joyeusement la pratique sans risque de faire de grosses bêtises. Vous apprendrez à identifier les composants et leur rôle (résistances, condensateurs, bobines, diodes, transistors, rela...

Encyclopédies du voyage et Cartoville. Pourquoi deux guides Gallimard consacrés à Lausanne ? Encyclopédies du voyage and Cartoville. Why two Gallimard guides of Lausanne?

Directory of Open Access Journals (Sweden)

Ariane Devanthéry

2009-10-01

Full Text Available Sur la route des voyageurs depuis plus de trois siècles et jouissant d’une localisation remarquable, la ville de Lausanne est une entrée courante des guides de voyage. Récemment, on a même vu les guides qui lui sont dédiés se multiplier de manière étonnante. Si l’on comprend clairement l’intérêt que les différentes maisons d’édition y trouvent, ainsi que les particularités de chacune de leurs réalisations, on peut toutefois s’interroger sur l’avantage que peut avoir un même éditeur à faire paraître deux guides distincts sur le même lieu. Et si la différence tenait justement au paysage ?Lausanne, part of travellers’ repertoire for over three centuries, enjoys a unique location and is frequently mentioned in travel guides. Guides devoted to it have mushroomed in the past few years. It is easy to understand the interest of Publishing Houses, just as the particular topics explored in their individual guides. Yet one still wonders what benefit a publisher may draw by issuing two distinct guides of the very same place. What if the difference lay precisely in the landscape?

Resolution no. 15/2012 Safety Guide for the practice of nuclear meters

International Nuclear Information System (INIS)

2012-01-01

1. This guide is Intended to complement the requirements for practice Nuclear meters out in September: • Joint Resolution CITMA-MINSAP Regulation Basic Standards Radiation safety of November 30, 2001, hereinafter NBS. • CITMA Resolution 121/2000, Regulations for the Safe Transport Radioactive Materials; hereinafter transport regulations. • Resolution 35/2003 of CITMA Regulation for the safe management of Radioactive waste of March 7, 2003, hereinafter Regulation waste. • Joint Resolution CITMA-MINSAP Regulations for the Selection, Training Authorization and Associated Personnel performing Employment Practices of Ionizing Radiation of December 19, 2003, hereinafter Staff Rules. 2. The requirements of this guide are applicable to entities and performing practice-related activities Nuclear Meters throughout the national territory.

Building competence in radiation protection and the safe use of radiation sources. Safety guide (Spanish ed.)

International Nuclear Information System (INIS)

2010-01-01

This Safety Guide makes recommendations concerning the building of competence in protection and safety within a national radiation protection infrastructure and provides guidance for setting up the structure for a national strategy. It relates to the training and assessment of qualification of new personnel and the retraining of existing personnel in order to develop and maintain appropriate levels of competence. It provides the necessary guidance to meet the requirements laid down in Safety Series No. 115, International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. Contents: 1. Introduction; 2. Responsibilities for building competence in protection and safety; 3. Education, training and work experience; 4. A national strategy for building competence in protection and safety.

Building competence in radiation protection and the safe use of radiation sources. Safety guide (Arabic ed.)

International Nuclear Information System (INIS)

2006-01-01

This Safety Guide makes recommendations concerning the building of competence in protection and safety within a national radiation protection infrastructure and provides guidance for setting up the structure for a national strategy. It relates to the training and assessment of qualification of new personnel and the retraining of existing personnel in order to develop and maintain appropriate levels of competence. It provides the necessary guidance to meet the requirements laid down in Safety Series No. 115, International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. Contents: 1. Introduction; 2. Responsibilities for building competence in protection and safety; 3. Education, training and work experience; 4. A national strategy for building competence in protection and safety.

Les manifestations cardiovasculaires chez les hemodialyses ...

African Journals Online (AJOL)

Le but de l'étude est d'analyser sur une période de 12 mois chez 75 patients en hémodialyse chronique, âgés de 38ans en moyenne, le les aspects cliniques, thérapeutiques et évolutifs des manifestations cardiovasculaires. La prévalence est de 87,20% chez les patients. Les signes fonctionnels les plus fréquents sont la ...

The management system for the disposal of radioactive waste. Safety guide

International Nuclear Information System (INIS)

2008-01-01

The objective of this Safety Guide is to provide recommendations on developing and implementing management systems for all phases of facilities for the disposal of radioactive waste and related activities. It covers the management systems for managing the different stages of waste disposal facilities, such as siting, design and construction, operation (i.e. the activities, which can extend over several decades, involving receipt of the waste product in its final packaging (if it is to be disposed of in packaged form), waste emplacement in the waste disposal facility, backfilling and sealing, and any subsequent period prior to closure), closure and the period of institutional control (i.e. either active control - monitoring, surveillance and remediation; or passive control - restricted land use). The management systems apply to various types of disposal facility for different categories of radioactive waste, such as: near surface (for low level waste), geological (for low, intermediate and/or high level waste), boreholes (for sealed sources), surface impoundment (for mining and milling waste) and landfill (for very low level waste). It also covers management systems for related processes and activities, such as extended monitoring and surveillance during the period of active institutional control in the post-closure phase, safety and performance assessments and development of the safety case for the waste disposal facility and regulatory authorization (e.g. licensing). This Safety Guide is intended to be used by organizations that are directly involved in, or that regulate, the facilities and activities described in paras 1.15 and 1.16, and by the suppliers of nuclear safety related products that are required to meet some or all of the requirements established in IAEA Safety Standards Series No. GS-R-3 'The Management System for Facilities and Activities'. It will also be useful to legislators and to members of the public and other parties interested in the nuclear

External Events Excluding Earthquakes in the Design of Nuclear Power Plants. Safety Guide

International Nuclear Information System (INIS)

2008-01-01

This Safety Guide provides recommendations and guidance on design for the protection of nuclear power plants from the effects of external events (excluding earthquakes), i.e. events that originate either off the site or within the boundaries of the site but from sources that are not directly involved in the operational states of the nuclear power plant units. In addition, it provides recommendations on engineering related matters in order to comply with the safety objectives and requirements established in the IAEA Safety Requirements publication, Safety of Nuclear Power Plants: Design. It is also applicable to the design and safety assessment of items important to the safety of land based stationary nuclear power plants with water cooled reactors. Contents: 1. Introduction; 2. Application of safety criteria to the design; 3. Design basis for external events; 4. Aircraft crash; 5. External fire; 6. Explosions; 7. Asphyxiant and toxic gases; 8. Corrosive and radioactive gases and liquids; 9. Electromagnetic interference; 10. Floods; 11. Extreme winds; 12. Extreme meteorological conditions; 13. Biological phenomena; 14. Volcanism; 15. Collisions of floating bodies with water intakes and UHS components; Annex I: Aircraft crashes; Annex II: Detonation and deflagration; Annex III: Toxicity limits.

Radiological design guide

International Nuclear Information System (INIS)

Evans, R.A.

1994-01-01

The purpose of this design guide is to provide radiological safety requirements, standards, and information necessary for designing facilities that will operate without unacceptable risk to personnel, the public, or the environment as required by the US Department of Energy (DOE). This design guide, together with WHC-CM-4-29, Nuclear Criticality Safety, WHC-CM-4-46, Nonreactor Facility Safety Analysis, and WHC-CM-7-5, Environmental Compliance, covers the radiation safety design requirements at Westinghouse Hanford Company (WHC). This design guide applies to the design of all new facilities. The WHC organization with line responsibility for design shall determine to what extent this design guide shall apply to the modifications to existing facilities. In making this determination, consideration shall include a cost versus benefit study. Specifically, facilities that store, handle, or process radioactive materials will be covered. This design guide replaces WHC-CM-4-9 and is designated a living document. This design guide is intended for design purposes only. Design criteria are different from operational criteria and often more stringent. Criteria that might be acceptable for operations might not be adequate for design

The operating organization and the recruitment, training and qualification of personnel for research reactors. Safety guide

International Nuclear Information System (INIS)

2008-01-01

This Safety Guide provides recommendations on meeting the requirements on the operating organization and on personnel for research reactors. It covers the typical operating organization for research reactor facilities; the recruitment process and qualification in terms of education, training and experience; programmes for initial and continuing training; the authorization process for those individuals having an immediate bearing on safety; and the processes for their requalification and reauthorization

Les rôles sexospécifiques et la violence dans les villes | CRDI ...

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

20 oct. 2017 ... Une croissance rapide et des identités sexuelles ancrées favorisent la violence ... services des villes mettent les femmes et les minorités sexuelles en danger. .... Une étude de cas sur les femmes et les transports à Guwahati ...

30 CFR 75.1429 - Guide ropes.

Science.gov (United States)

2010-07-01

... Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Hoisting and Mantrips Wire Ropes § 75.1429 Guide ropes. If guide... strength (manufacturer's published catalog strength) of the guide rope at installation shall meet the...

Les équipes du programme Innovation pour la santé des mères et ...

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

29 sept. 2017 ... Tant les chercheurs que les responsables de politiques ont profité des séances de renforcement des compétences, ou « cafés du savoir », pour en ... Au Nigéria, par exemple, des chercheurs testent l'efficacité d'un nouveau guide à permettre aux sages-femmes des communautés à reconnaître et à traiter ...

Guide d'application de la réglementation incendie

CERN Document Server

2012-01-01

Vous trouverez dans ce guide, de nombreux schémas et tableaux de synthèses, associés aux recommandations et alertes de l'auteur qui permettent d'aborder la problématique de la sécurité incendie étape par étape en identifiant clairement les dispositions à mettre en œuvre selon le type de construction. Pour chaque type de locaux, les principes de sécurité, le classement des bâtiments, les dispositions constructives, le désenfumage, les règles d'aménagement, les installations techniques ainsi que les moyens de secours sont décrits et commentés. Des cas spécifiques, tels que les logements-foyers, les parcs de stationnement ou les grandes cuisines (ERP) sont abordés. Pour les ERP, les dispositions de sécurité sont développées en tenant compte des spécificités des 15 types d'établissements les plus courants. Cette édition prend en compte les dernières évolutions réglementaires intégrées et/ou des précisions sur certains points : - installations de détecteurs de fumée dans les hab...

Development of Draft Regulatory Guide on Accident Analysis for Nuclear Power Plants with New Safety Design Features

Energy Technology Data Exchange (ETDEWEB)

Bang, Young Seok; Woo, Sweng Woong; Hwang, Tae Suk [KINS, Daejeon (Korea, Republic of); Sim, Suk K; Hwang, Min Jeong [Environment and Energy Technology, Daejeon (Korea, Republic of)

2016-05-15

The present paper discusses the development process of the draft version of regulatory guide (DRG) on accident analysis of the NPP having the NSFD and its result. Based on the consideration on the lesson learned from the previous licensing review, a draft regulatory guide (DRG) on accident analysis for NPP with new safety design features (NSDF) was developed. New safety design features (NSDF) have been introduced to the new constructing nuclear power plants (NPP) since the early 2000 and the issuance of construction permit of SKN Units 3 and 4. Typical examples of the new safety features includes Fluidic Device (FD) within Safety Injection Tanks (SIT), Passive Auxiliary Feedwater System (PAFS), ECCS Core Barrel Duct (ECBD) which were adopted in APR1400 design and/or APR+ design to improve the safety margin of the plants for the postulated accidents of interest. Also several studies of new concept of the safety system such as Hybrid ECCS design have been reported. General and/or specific guideline of accident analysis considering the NSDF has been requested. Realistic evaluation of the impact of NSDF on accident with uncertainty and separated accident analysis accounting the NSDF impact were specified in the DRG. Per the developmental process, identification of key issues, demonstration of the DRG with specific accident with specific NSDF, and improvement of DGR for the key issues and their resolution will be conducted.

Nuclear criticality safety guide

International Nuclear Information System (INIS)

Pruvost, N.L.; Paxton, H.C.

1996-09-01

This technical reference document cites information related to nuclear criticality safety principles, experience, and practice. The document also provides general guidance for criticality safety personnel and regulators

Nuclear criticality safety guide

Energy Technology Data Exchange (ETDEWEB)

Pruvost, N.L.; Paxton, H.C. [eds.

1996-09-01

This technical reference document cites information related to nuclear criticality safety principles, experience, and practice. The document also provides general guidance for criticality safety personnel and regulators.

Ageing Management for Nuclear Power Plants. Safety Guide (Russian Edition); Upravlenie stareniem atomnykh ehlektrostantsij. Rukovodstvo po bezopasnosti

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-01-15

The median age of nuclear power plants connected to the grid worldwide is increasing. Ageing management has become an important issue in ensuring the availability of required safety functions throughout the service life of a plant. This Safety Guide provides recommendations on meeting the requirements for safe long term operation and identifies key elements of effective ageing management for nuclear power plants.

Safety Training: Ergonomie - Sensibilisation aux gestes et postures de travail

CERN Multimedia

Laetitia Laddada

2004-01-01

Nous vous proposons un nouveau cours d'ergonomie (durée : 1 jour) Sensibilisation aux gestes et postures de travail. A l'issue de cette formation, vous serez capable d'adopter et d'appliquer les principes de base de sécurité physique et d'économie d'efforts dans les manipulations d'objets. Les cours sont pris en charge par la Commission de Sécurité. L'inscription EDH est obligatoire. Pour plus d'information, veuillez consulter les pages Formation & Développement (Groupe Sécurité). FORMATION EN SECURITE SAFETY TRAINING Laetitia Laddada 73811 - 79236 safety.training@cern.ch

Cooperative development of nuclear safety regulations, guides and standards based on NUSS

International Nuclear Information System (INIS)

Pachner, J.; Boyd, F.C.; Yaremy, E.M.

1984-10-01

In 1983, the Atomic Energy Control Board and Atomic Energy of Canada Limited conducted a study of a possible joint program involving Canada, a nuclear power plant importing Member State and the IAEA for the development of the national nuclear safety regulations and guides based on NUSS documents. During the study, a work plan with manpower estimates for the development of design was prepared as an investigatory exercise. The work plan suggests that a successful NUSS implementation in developing Member States will require availability of significant resources at the start of the program. The study showed that such a joint program could provide an effective mechanism for transfer of nuclear safety know-how to the developing Member States through NUSS implementation

The IAEA's activities in safeguarding nuclear materials and in developing internationally acceptable safety codes and guides for nuclear power plants

International Nuclear Information System (INIS)

Rometsch, Rudolf; Specter, Herschel

1977-01-01

Promoting the peaceful use of nuclear energy and aiming at the international sharing of its benefits are objectives that guide the activities of the Agency. But this promotional work is carried out on condition that security and safety are provided for. All Agency assistance involving nuclear facilities will be subjected to standards of safety or other standards, which are proposed by a State the Agency finds essentially equivalent. Safeguards are always applied on the basis of agreement. States party to NPT are obligated to negotiate and conclude with the Agency agreements which cover all their peaceful nuclear activities. Safeguards agreements concluded outside NPT are applied to specific supplies of facilities, equipment and material. To assist countries in laying down their nuclear safety regulations the Agency's program for the developing of codesof practice and safety guides for nuclear power plants draws up guidelines for governmental organizations, siting, design, operation and quality assurance. Codes are the fundamental documents laying down the objectives of each field of nuclear safety

Safety Training: Sensibilisation aux gestes et postures de travail

CERN Multimedia

Laetitia Laddada

2004-01-01

Nous vous proposons un nouveau cours de sécurité lié aux manutentions manuelles (durée 1 jour) : Sensibilisation aux gestes et postures de travail. Si vous êtes amené à manipuler régulièrement des charges lourdes ou volumineuses, cette formation peut vous aider à prévenir les lésions musculaires ou dorsales. A l'issue de cette formation, vous serez capable d'adopter et d'appliquer les principes de base de sécurité physique et d'économie d'efforts dans les manipulations d'objets. Les cours sont pris en charge par la Commission de Sécurité. L'inscription EDH est obligatoire. Pour plus d'information, veuillez consulter les pages Formation & Développement (Groupe Sécurité). FORMATION EN SECURITE SAFETY TRAINING Laetitia Laddada 73811 - 79236 safety.training@cern.ch

Excision Les jeunes changent l'Afrique par les TIC

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

Comité Inter-Africain sur les Pratiques Traditionnelles ayant effet sur la santé des ... Planche 7 - Perception genrée de la citoyenneté : les dire des femmes. 90 ...... dans le monde avec les migrations internationales, l'excision ne semble pas être ...... En utilisant les TIC pour exprimer leurs attentes et leurs besoins, les jeunes, ...

Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material. Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2010-01-01

This Safety Guide provides recommendations on achieving and demonstrating compliance with IAEA Safety Standards Series No. TS-R-1, Regulations for the Safe Transport of Radioactive Material, 2005 Edition, establishing safety requirements to be applied to the national and international transport of radioactive material. Transport is deemed to comprise all operations and conditions associated with and involved in the movement of radioactive material; these include the design, fabrication and maintenance of packaging, and the preparation, consigning, handling, carriage, storage in transit and receipt at the final destination of packages. This publication supersedes IAEA Safety Series No. TS-G-1.1, 2002 Edition

Safety measurement and monitoring in healthcare: a framework to guide clinical teams and healthcare organisations in maintaining safety

Science.gov (United States)

Vincent, Charles; Burnett, Susan; Carthey, Jane

2014-01-01

Patients, clinicians and managers all want to be reassured that their healthcare organisation is safe. But there is no consensus about what we mean when we ask whether a healthcare organisation is safe or how this is achieved. In the UK, the measurement of harm, so important in the evolution of patient safety, has been neglected in favour of incident reporting. The use of softer intelligence for monitoring and anticipation of problems receives little mention in official policy. The Francis Inquiry report into patient treatment at the Mid Staffordshire NHS Foundation Trust set out 29 recommendations on measurement, more than on any other topic, and set the measurement of safety an absolute priority for healthcare organisations. The Berwick review found that most healthcare organisations at present have very little capacity to analyse, monitor or learn from safety and quality information. This paper summarises the findings of a more extensive report and proposes a framework which can guide clinical teams and healthcare organisations in the measurement and monitoring of safety and in reviewing progress against safety objectives. The framework has been used so far to promote self-reflection at both board and clinical team level, to stimulate an organisational check or analysis in the gaps of information and to promote discussion of ‘what could we do differently’. PMID:24764136

Repenser le risque et les catastrophes dans les régions de montagne

Directory of Open Access Journals (Sweden)

Kenneth Hewitt

2012-03-01

vie quotidienne des peuples montagnards, les catastrophes environnementales sont bien souvent dépendantes d’autres formes sociales de risque, de vulnérabilité et d’une insécurité corollaire. Pour conclure, la marginalisation des espaces montagnards reste avant tout la conséquence du développement socio-économique de ces territoires, dont les paramètres dépendent des stratégies de développement de l’État et des acteurs métropolitains et internationaux.This chapter presents a view of risk and disaster in the mountains that finds them fully a part of public safety issues in modern states and developments, rather than separated from them. This contrasts with prevailing approaches to disaster focused on natural hazards, “unscheduled” or extreme events, and emergency preparedness; approaches strongly reinforced by mountain stereotypes. Rather, we find the legacies of social and economic histories, especially relations to down-country or metropolitan actors, are decisive in shaping contemporary “mountain realities”. Developments in transportation, resource extraction and tourism that serve state and international agendas can increase rather than reduce risks for mountain populations, and undermine pre-existing strategies to minimise environmental dangers. Above all, we see rapid urbanisation in mountains generally and the Himalaya in particular as highly implicated in exacerbating risks and creating new types of vulnerabilities. Enforced displacement, and concentration of, people in urban agglomerations, is a major part of the modern history of mountain lands that invites more careful exploration. Rapid expansion of built environments and infrastructure, without due regard to hazards and structural safety, introduce new and complex risks, while altering older equations with and to the land and sapping people’s resilience. In the lives of mountain people, environmental hazards are mostly subordinate to other, societal sources of risk and

IAEA Safety Standards

International Nuclear Information System (INIS)

2016-09-01

The IAEA Safety Standards Series comprises publications of a regulatory nature covering nuclear safety, radiation protection, radioactive waste management, the transport of radioactive material, the safety of nuclear fuel cycle facilities and management systems. These publications are issued under the terms of Article III of the IAEA’s Statute, which authorizes the IAEA to establish “standards of safety for protection of health and minimization of danger to life and property”. Safety standards are categorized into: • Safety Fundamentals, stating the basic objective, concepts and principles of safety; • Safety Requirements, establishing the requirements that must be fulfilled to ensure safety; and • Safety Guides, recommending measures for complying with these requirements for safety. For numbering purposes, the IAEA Safety Standards Series is subdivided into General Safety Requirements and General Safety Guides (GSR and GSG), which are applicable to all types of facilities and activities, and Specific Safety Requirements and Specific Safety Guides (SSR and SSG), which are for application in particular thematic areas. This booklet lists all current IAEA Safety Standards, including those forthcoming

Safety training: Ergonomie - Sensibilisation à l'ergonomie bureautique

CERN Multimedia

Laetitia Laddada

2004-01-01

Nous vous proposons une 1/2 journée de sensibilisation sur les risques engendrés par une mauvaise posture lors du travail sur écran (mal de dos, fatigue visuelle, douleurs des poignets...) et des bonnes pratiques pour y remédier. Les prochaines sessions auront lieu le 8 juillet 2004. Les cours sont pris en charge par la Commission de Sécurité et animés par Pily Clemente et Marion Ribordy de « PM postures » . L'inscription via EDH est obligatoire. Pour plus d'information et inscription par EDH à ce cours, veuillez consulter les pages Formation et Développement (groupe sécurité) de HR, ou contacter l'organisateur. Les places seront attribuées dans l'ordre de réception des inscriptions. Organisateur : Ana-Paula Bernardes/SC-GS (71385) Ana-paula.bernardes@cern.chFORMATION EN SECURITE SAFETY TRAINING Laetitia Laddada 73811 - 79236 safety.training@cern.ch

Réduire les risques et les pertes attribuables aux changements ...

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

22 août 2014 ... Entre-temps, dans les pays plus riches, comme le Japon et les États‑Unis, les bâtiments et l'infrastructure font l'objet de nouvelles conceptions visant à prévenir les conséquences des tremblements de terre. Quelle comparaison feriez‑vous entre les plans d'adaptation aux tremblements de terre et les ...

Les changements climatiques brouillent les prédictions des faiseurs ...

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

8 oct. 2010 ... Depuis des générations, les autochtones de l'ouest du Kenya comptent sur les pouvoirs mystiques que possèdent les « faiseurs de pluie » du clan Nganyi pour prédire la météo. Cependant, le temps instable amené par les changements climatiques brouille les indices grâce auxquels les faiseurs de pluie ...

The IAEA safety standards

International Nuclear Information System (INIS)

Karbassioun, Ahmad

1995-01-01

During the development of the NUSS standards, wide consultation was carried out with all the Member States to obtain a consensus and the programme was supervised by a Senior Advisory Group consisting of senior safety experts from 13 countries. This group of senior regulators later became what is now known as the Nuclear Safety Standards Advisory Group (NUSSAG) and comprises of senior regulatory experts from 16 countries. The standards that were developed comprise of four types of documents: safety fundamentals; codes of practice; safety guides; and safety practices. The safety fundamentals set out the basic objectives, concepts and principles for nuclear safety in nuclear power plants. The codes of practice, are of a legislative nature, and establish the general objectives that must be fulfilled to ensure adequate nuclear power plant safety. They cover five areas: governmental organization; siting, design, operation and quality assurance. The safety guides, administrative in character, recommend procedures and acceptable technical solutions to implement the codes and guides by presenting further details gained from Member States, on the application and interpretation of individual concepts in the NUSS codes and guides. In total in the NUSS series there is currently one Fundamentals document, five Codes of Practice and fifty-six Safety Guides

Crowdsourcing a les institucions de la memòria : les transcripcions massives

Directory of Open Access Journals (Sweden)

Alcalá Ponce de León, Mireia

2015-12-01

Full Text Available En els últims anys, la participació social per mitjà de la xarxa ha esdevingut essencial en alguns àmbits. En aquest treball es fa referència a aquest tipus de moviment anomenat “crowdsourcing” o de “proveïment participatiu”, a la figura del voluntariat i a les motivacions que el porten a participar-hi. A més, es mostra un recull dels principals projectes de “crowdsourcing” sobre transcripcions massives realitzats a les institucions de la memòria (biblioteques, arxius, museus i les galeries a nivell internacional. Mitjançant l’anàlisi d’aquests projectes, se’n revisen les característiques a través d’uns indicadors creats especialment per aquests tipus d’iniciatives i, a partir d’aquí, es proposen unes bones pràctiques que cal preveure en el disseny de projectes de transcripcions massives.En los últimos años, la participación social a través de la red se ha convertido en esencial en algunos ámbitos. En este trabajo se hace referencia a este tipo de movimientos llamados “crowdsourcing” o de “abastecimiento participativo”, a la figura del voluntariado y a las motivaciones que le llevan a participar. Además, se muestra una recopilación de los principales proyectos deIn recent years, the growth of web-based social participation and the open source movement have prompted a number of initiatives, including the movement known as crowdsourcing . This paper examines crowdsourcing as a volunteering phenomenon and considers what motivates individuals to participate in crowdsourcing. In addition, the paper reviews the main projects in mass transcription being made in memory institutions worldwide (libraries, archives, museums and galleries, briefly introducing each project and analyzing its main features. Finally, a selection of best practices is offered to guide institutions in the implementation of mass transcription projects.

Former les jeunes chercheurs en vue d'influencer les politiques de ...

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

2 mai 2016 ... Les conférences, les séances de tutorat et les stages financés par le CRDI en Asie, en Afrique et en Amérique latine renforcent les capacités des jeunes chercheurs en vue d'éclairer les politiques de télécommunications. Communications Policy Research South (CPRsouth) : les conférences présentent les ...

Radiation protection and safety guide no. GRPB-G-1: qualification and certification of radiation protection personnel

International Nuclear Information System (INIS)

Schandorf, C.; Darko, O.; Yeboah, J.; Osei, E.K.; Asiamah, S.D.

1995-01-01

A number of accidents with radiation sources are invariably due to human factors. The achievement and maintenance of proficiency in protection and safety in working with radiation devices is a necessary prerequisite. This guide specifies the national scheme and minimum requirements for qualification and certification of radiation protection personnel. The objective is to ensure adequate level of skilled personnel by continuous upgrading of knowledge and skill of personnel. The following sectors are covered by this guide: medicine, industry, research and training, nuclear facility operations, miscellaneous activities

General design safety principles for nuclear power plants

International Nuclear Information System (INIS)

1986-01-01

This Safety Guide provides the safety principles and the approach that have been used to implement the Code in the Safety Guides. These safety principles and the approach are tied closely to the safety analyses needed to assist the design process, and are used to verify the adequacy of nuclear power plant designs. This Guide also provides a framework for the use of other design Safety Guides. However, although it explains the principles on which the other Safety Guides are based, the requirements for specific applications of these principles are mostly found in the other Guides

Schedules of Provisions of the IAEA Regulations for the Safe Transport of Radioactive Material (2009 Ed.). Safety Guide

International Nuclear Information System (INIS)

2014-01-01

This Safety Guide is issued in support of Regulations for the Safe Transport of Radioactive Material (IAEA Safety Standards Series No. TS-R-1, 2009 Edition). It lists the paragraph numbers of the Transport Regulations that are relevant for specified types of consignment, classified according to their UN numbers. It does not provide additional recommendations. The intended users are consignors and consignees, carriers, shippers, regulators, and end users involved in the transport of radioactive material. A person or organization intending to transport a particular type of consignment of radioactive material must meet requirements in all sections of the Transport Regulations. This Safety Guide aids users by providing a listing of the relevant requirements of the Transport Regulations for each type of radioactive material, package or shipment. Once a consignor has classified the radioactive material to be shipped, the appropriate UN number can be assigned and the paragraph numbers of the requirements that apply for the shipment can be found in the corresponding schedule

Ultrasonography-guided Transthoracic Cutting Biopsy of Pulmonary Lesion: Diagnostic Benefits and Safety

Energy Technology Data Exchange (ETDEWEB)

Yang, Mei Ah; Park, Mi Hyun [Dankook University Hospital, Cheonan (Korea, Republic of); Shin, Byung Seok [Chungnam National University Hospital, Daejeon (Korea, Republic of); Ohm, Joon Young [Bucheon St. Mary' s Hospital, Bucheon (Korea, Republic of)

2012-06-15

To assess the safety and usefulness of ultrasonography-guided transthoracic cutting biopsy for lung lesions. Eighty-eight patients (66 men, 22 women, mean age 59 years) with lung lesions underwent an ultrasonography(USG)-guided transthoracic cutting biopsy. The final diagnosis was based on the findings of surgery and clinical and radiological follow-ups. The histopathologic results and diagnostic accuracy of cutting biopsy were determined. Also, the complication rate was statistically evaluated according to the mass size, number of biopsies, and the presence or absence of pleural effusion. Biopsy specimens were successfully obtained in all patients. 79 of 88 lesions (89.8%) were established by histopathology. The final diagnosis was malignant in 58 and benign in 28. The remaining 2 patients were lost to follow-up. Diagnostic sensitivity for malignant lesions was 89.6% (52/58) and that for benign lesions was 96.4% (27/28). Procedure-related complications occurred in 9 patients (10.2%) including pneumothorax (n = 2) and hemoptysis (n = 7). And there was no significant difference according to mass size, number of biopsies, or presence of pleural effusion. USG-guided transthoracic cutting biopsy is a useful and safe method for technically-feasible lung lesions

Ultrasonography-guided Transthoracic Cutting Biopsy of Pulmonary Lesion: Diagnostic Benefits and Safety

International Nuclear Information System (INIS)

Yang, Mei Ah; Park, Mi Hyun; Shin, Byung Seok; Ohm, Joon Young

2012-01-01

To assess the safety and usefulness of ultrasonography-guided transthoracic cutting biopsy for lung lesions. Eighty-eight patients (66 men, 22 women, mean age 59 years) with lung lesions underwent an ultrasonography(USG)-guided transthoracic cutting biopsy. The final diagnosis was based on the findings of surgery and clinical and radiological follow-ups. The histopathologic results and diagnostic accuracy of cutting biopsy were determined. Also, the complication rate was statistically evaluated according to the mass size, number of biopsies, and the presence or absence of pleural effusion. Biopsy specimens were successfully obtained in all patients. 79 of 88 lesions (89.8%) were established by histopathology. The final diagnosis was malignant in 58 and benign in 28. The remaining 2 patients were lost to follow-up. Diagnostic sensitivity for malignant lesions was 89.6% (52/58) and that for benign lesions was 96.4% (27/28). Procedure-related complications occurred in 9 patients (10.2%) including pneumothorax (n = 2) and hemoptysis (n = 7). And there was no significant difference according to mass size, number of biopsies, or presence of pleural effusion. USG-guided transthoracic cutting biopsy is a useful and safe method for technically-feasible lung lesions

Guide on a national system for collecting, assessing and disseminating information on safety-related events in nuclear power plants

International Nuclear Information System (INIS)

1983-02-01

There is a wide spectrum of safety significance in the events that can occur during nuclear power plant operations. It is important that lessons be learned from safety-related events (hereinafter referred to as unusual events) so as to improve the safety of nuclear power plants. Hence formal procedures should be established for this purpose. The purpose of this document is to provide guidance to Member States for establishing a system (hereinafter referred to as a national system) for collecting, storing, retrieving, assessing and disseminating information on unusual events in nuclear power plants. The guidance given is based on experience gained in the use of existing national and international systems. This guide covers a national system that is part of a programme to improve nuclear power plant safety using experience gained from operating plants both within and outside the country. Implementing the recommendations in this guide would render any national system compatible with other national systems and facilitate the participation in the IAEA System for Reporting Unusual Events with Safety Significance (hereinafter referred to as the IAEA Incident Reporting System, IAEA-IRS) for more widespread dissemination of lessons learned from nuclear power plant operation

Packaging review guide for reviewing safety analysis reports for packagings: Revision 1

International Nuclear Information System (INIS)

Fisher, L.E.; Chou, C.K.; Lloyd, W.R.; Mount, M.E.; Nelson, T.A.; Schwartz, M.W.; Witte, M.C.

1988-10-01

The Department of Energy (DOE) has established procedures for obtaining certification of packagings used by DOE and its contractors for the transport of radioactive materials. The principal purpose of this document is to assure the quality and uniformity of PCS reviews and to present a well-defined base from which to evaluate proposed changes in the scope and requirements of reviews. The Packaging Review Guide (PRG) also sets forth solutions and approaches determined to be acceptable in the past in dealing with a specific safety issue or safety-related design area. These solutions and approaches are presented in this form so that reviewers can take consistent and well-understood positions as the same safety issues arise in future cases. An applicant submitting a SARP does not have to follow the solutions or approaches presented. It is also a purpose of the PRG to make information about DOE certification policy and procedures widely available to DOE field offices, DOE contractors, federal agencies, and interested members of the public. 77 refs., 16 figs., 15 tabs

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

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-09-15

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

Safety Training: Ergonomie - Sensibilisation à l'ergonomie bureautique

CERN Multimedia

2005-01-01

Nous vous proposons une 1/2 journée de sensibilisation sur les risques engendrés par une mauvaise posture lors du travail sur écran (mal de dos, fatigue visuelle, douleurs des poignets...) et des bonnes pratiques pour y remédier. Les prochaines sessions auront lieu le 24 février 2005 (matin et après-midi). Les cours sont pris en charge par la Commission de Sécurité et animés par Pily Clemente et Marion Ribordy de « PM postures ». L'inscription via EDH est obligatoire. Pour plus d'information et inscription par EDH à ce cours, veuillez consulter les pages Formation et Développement (groupe sécurité) de HR, ou contacter l'organisateur. Les places seront attribuées dans l'ordre de réception des inscriptions. Organisateur : Ana-Paula Bernardes/SC-GS (71385) Ana-paula.bernardes@cern.ch FORMATION EN SECURITE SAFETY TRAINING safety.training@ce...

Safety Training: Sensibilisation aux gestes et postures de travail

CERN Multimedia

Laetitia Laddada

2004-01-01

Nous vous proposons un nouveau cours de sécurité lié aux manutentions manuelles (durée 1 jour) : Sensibilisation aux gestes et postures de travail. Si vous êtes amené à manipuler régulièrement des charges lourdes ou volumineuses, cette formation peut vous aider à prévenir les lésions musculaires ou dorsales. A l'issue de cette formation, vous serez capable d'adopter et d'appliquer les principes de base de sécurité physique et d'économie d'efforts dans les manipulations d'objets. Les cours sont pris en charge par la Commission de Sécurité. L'inscription EDH est obligatoire. Pour plus d'information, veuillez consulter les pages Formation & Développement (Groupe Sécurité). Formation & Développement (Groupe Sécurité) FORMATION EN SECURITE SAFETY TRAINING Laetitia Laddada 73811 - 79236 safety.training@cern.ch

Mesurer et comparer les contextes et les politiques alimentaires en ...

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

En Amérique latine, les maladies non transmissibles (MNT) sont responsables de trois décès sur quatre. Une mauvaise alimentation fait augmenter de plus en plus les décès et les maladies évitables et prématurées liés aux MNT. Dans le but de régler ce problème, ce projet suivra et comparera les contextes et les ...

Categorization of Radioactive Sources. Safety Guide

International Nuclear Information System (INIS)

2009-01-01

The IAEA's Statute authorizes the Agency to establish safety standards to protect health and minimize danger to life and property - standards which the IAEA must use in its own operations, and which a State can apply by means of its regulatory provisions for nuclear and radiation safety. A comprehensive body of safety standards under regular review, together with the IAEA's assistance in their application, has become a key element in a global safety regime. In the mid-1990s, a major overhaul of the IAEA's safety standards programme was initiated, with a revised oversight committee structure and a systematic approach to updating the entire corpus of standards. The new standards that have resulted are of a high calibre and reflect best practices in Member States. With the assistance of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its safety standards. Safety standards are only effective, however, if they are properly applied in practice. The IAEA's safety services - which range in scope from engineering safety, operational safety, and radiation, transport and waste safety to regulatory matters and safety culture in organizations - assist Member States in applying the standards and appraise their effectiveness. These safety services enable valuable insights to be shared and I continue to urge all Member States to make use of them. Regulating nuclear and radiation safety is a national responsibility, and many Member States have decided to adopt the IAEA's safety standards for use in their national regulations. For the Contracting Parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions. The standards are also applied by designers, manufacturers and operators around the world to enhance nuclear and radiation safety in power generation, medicine, industry, agriculture, research and education

Ultrasound-guided lumbar puncture in pediatric patients: technical success and safety.

Science.gov (United States)

Pierce, David B; Shivaram, Giri; Koo, Kevin S H; Shaw, Dennis W W; Meyer, Kirby F; Monroe, Eric J

2018-06-01

Disadvantages of fluoroscopically guided lumbar puncture include delivery of ionizing radiation and limited resolution of incompletely ossified posterior elements. Ultrasound (US) allows visualization of critical soft tissues and the cerebrospinal fluid (CSF) space without ionizing radiation. To determine the technical success and safety of US-guided lumbar puncture in pediatric patients. A retrospective review identified all patients referred to interventional radiology for lumbar puncture between June 2010 and June 2017. Patients who underwent lumbar puncture with fluoroscopic guidance alone were excluded. For the remaining procedures, technical success and procedural complications were assessed. Two hundred and one image-guided lumbar punctures in 161 patients were included. Eighty patients (43%) had previously failed landmark-based attempts. One hundred ninety-six (97.5%) patients underwent lumbar puncture. Five procedures (2.5%) were not attempted after US assessment, either due to a paucity of CSF or unsafe window for needle placement. Technical success was achieved in 187 (95.4%) of lumbar punctures attempted with US guidance. One hundred seventy-seven (90.3%) were technically successful with US alone (age range: 2 days-15 years, weight range: 1.9-53.1 kg) and an additional 10 (5.1%) were successful with US-guided thecal access and subsequent fluoroscopic confirmation. Three (1.5%) cases were unsuccessful with US guidance but were subsequently successful with fluoroscopic guidance. Of the 80 previously failed landmark-based lumbar punctures, 77 (96.3%) were successful with US guidance alone. There were no reported complications. US guidance is safe and effective for lumbar punctures and has specific advantages over fluoroscopy in pediatric patients.

Packaging Review Guide for Reviewing Safety Analysis Reports for Packagings

Energy Technology Data Exchange (ETDEWEB)

DiSabatino, A; Biswas, D; DeMicco, M; Fisher, L E; Hafner, R; Haslam, J; Mok, G; Patel, C; Russell, E

2007-04-12

This Packaging Review Guide (PRG) provides guidance for Department of Energy (DOE) review and approval of packagings to transport fissile and Type B quantities of radioactive material. It fulfills, in part, the requirements of DOE Order 460.1B for the Headquarters Certifying Official to establish standards and to provide guidance for the preparation of Safety Analysis Reports for Packagings (SARPs). This PRG is intended for use by the Headquarters Certifying Official and his or her review staff, DOE Secretarial offices, operations/field offices, and applicants for DOE packaging approval. This PRG is generally organized at the section level in a format similar to that recommended in Regulatory Guide 7.9 (RG 7.9). One notable exception is the addition of Section 9 (Quality Assurance), which is not included as a separate chapter in RG 7.9. Within each section, this PRG addresses the technical and regulatory bases for the review, the manner in which the review is accomplished, and findings that are generally applicable for a package that meets the approval standards. This Packaging Review Guide (PRG) provides guidance for DOE review and approval of packagings to transport fissile and Type B quantities of radioactive material. It fulfills, in part, the requirements of DOE O 460.1B for the Headquarters Certifying Official to establish standards and to provide guidance for the preparation of Safety Analysis Reports for Packagings (SARPs). This PRG is intended for use by the Headquarters Certifying Official and his review staff, DOE Secretarial offices, operations/field offices, and applicants for DOE packaging approval. The primary objectives of this PRG are to: (1) Summarize the regulatory requirements for package approval; (2) Describe the technical review procedures by which DOE determines that these requirements have been satisfied; (3) Establish and maintain the quality and uniformity of reviews; (4) Define the base from which to evaluate proposed changes in scope

Nursing Student Experiences Regarding Safe Use of Electronic Health Records: A Pilot Study of the Safety and Assurance Factors for EHR Resilience Guides.

Science.gov (United States)

Whitt, Karen J; Eden, Lacey; Merrill, Katreena Collette; Hughes, Mckenna

2017-01-01

Previous research has linked improper electronic health record configuration and use with adverse patient events. In response to this problem, the US Office of the National Coordinator for Health Information Technology developed the Safety and Assurance Factors for EHR Resilience guides to evaluate electronic health records for optimal use and safety features. During the course of their education, nursing students are exposed to a variety of clinical practice settings and electronic health records. This descriptive study evaluated 108 undergraduate and 51 graduate nursing students' ratings of electronic health record features and safe practices, as well as what they learned from utilizing the computerized provider order entry and clinician communication Safety and Assurance Factors for EHR Resilience guide checklists. More than 80% of the undergraduate and 70% of the graduate students reported that they experienced user problems with electronic health records in the past. More than 50% of the students felt that electronic health records contribute to adverse patient outcomes. Students reported that many of the features assessed were not fully implemented in their electronic health record. These findings highlight areas where electronic health records can be improved to optimize patient safety. The majority of students reported that utilizing the Safety and Assurance Factors for EHR Resilience guides increased their understanding of electronic health record features.

Les perspectives nutritionnelles offertes par les OGM en alimentation humaine

Directory of Open Access Journals (Sweden)

Pascal Gérard

2004-03-01

Full Text Available Une étude des brevets récents, des publications scientifiques ainsi que des documents présentant les projets des firmes de biotechnologie constituent la base de cet article qui présente les perspectives de développement en alimentation humaine des organismes génétiquement modifiés (OGM présentant un intérêt nutritionnel. Si l’on trouve dans les brevets et les publications scientifiques des applications qui concernent l’amélioration ou l’enrichissement de la composition en macro- et micronutriments, ces applications restent curieusement à l’état de projets, très loin de la mise sur le marché. Les critiques aussi bien que les louanges dont sont l’objet les rares cas dont on pourrait envisager une mise en œuvre à moyen terme, comme le « riz doré », sont aussi injustifiées et excessives les unes que les autres. Les violentes polémiques autour des OGM risquent de handicaper le développement d’une technique puissante, qui n’est certes pas indispensable pour apporter une solution à l’éradication de la faim dans le monde, mais qui peut apporter des améliorations à la nutrition des populations, aussi bien des populations des pays en développement que des pays développés.

Safety assessment of research reactors and preparation of the safety analysis report

International Nuclear Information System (INIS)

1994-01-01

This Safety Guide presents guidelines, approved by international consensus, for the preparation, review and assessment of safety documentation for research reactors such as the Safety Analysis Report. While the Guide is most applicable to research reactors in the design and construction stage, it is also recommended for use during relicensing or reassessment of existing reactors

Protéger les collectivités côtières du nord du Maroc | CRDI - Centre ...

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

3 févr. 2011 ... Élévation du niveau de la mer, ondes de tempête, inondations littorales : les ... Un plan d'action en matière de gestion intégrée du littoral et une nouvelle ... du territoire sans recourir à un guide de la dynamique du milieu côtier. ... local, et encore moins de contrôle sur les terres dont elles sont tributaires.

Design of the reactor coolant system and associated systems in nuclear power plants. Safety guide (Spanish Edition); Diseno del sistema de refrigeracion del reactor y los sistemas asociados en las centrales nucleares. Guia de seguridad

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-07-15

This Safety Guide was prepared under the IAEA programme for establishing safety standards for nuclear power plants. The basic requirements for the design of safety systems for nuclear power plants are established in the Safety Requirements publication, Safety Standards Series No. NS-R-1 on Safety of Nuclear Power Plants: Design, which it supplements. This Safety Guide describes how the requirements for the design of the reactor coolant system (RCS) and associated systems in nuclear power plants should be met. This publication is a revision and combination of two previous Safety Guides, Safety Series No. 50-SG-D6 on Ultimate Heat Sink and Directly Associated Heat Transport Systems for Nuclear Power Plants (1982), and Safety Series No. 50-SG-D13 on Reactor Coolant and Associated Systems in Nuclear Power Plants (1987), which are superseded by this new Safety Guide. The revision takes account of developments in the design of the RCS and associated systems in nuclear power plants since the earlier Safety Guides were published in 1982 and 1987, respectively. The other objectives of the revision are to ensure consistency with Ref., issued in 2004, and to update the technical content. In addition, an appendix on pressurized heavy water reactors (PHWRs) has been included.

Conduct of Operations at Nuclear Power Plants. Safety Guide (Spanish Edition); Realizacion de operaciones en centrales nucleares. Guia de seguridad

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-04-15

This Safety Guide identifies the main responsibilities and practices of nuclear power plant (NPP) operations departments in relation to their responsibility for the safe functioning of the plant. The guide presents the factors to be considered in structuring the operations department of an NPP; setting high standards of performance; making safety related decisions in an effective manner; conducting control room and field activities in a thorough and professional manner; and maintaining an NPP within established operational limits and conditions. Contents: 1. Introduction; 2. Management and organization of plant operations; 3. Shift complement and functions; 4. Shift routines and operating practices; 5. Control of equipment and plant status; 6. Operations equipment and operator aids; 7. Work control and authorization.

A Guide to Laser Safety

Energy Technology Data Exchange (ETDEWEB)

Davies, W M

1998-09-01

In one of the few volumes dedicated to laser safety to appear since the 'bible' of Sliney and Wolbarsht, Roy Henderson sets out to provide the reader with a practical account of both the philosophy and practice across contemporary application of lasers. The book is split into three sections. The first section is essentially a non-mathematical review of lasers, optical hazards and laser safety. It is intended as an easily digestible introduction to the subject, conveying the primary concepts of laser safety without the camouflage of equations. This piece of text is manifestly readable by all who have interest in the topic. The second section introduces more meat onto the bones introduced in the first section and some of the practical mathematics necessary to determine optical irradiance in simple laser beams. The book is not intended as a scientific treatise and rigorous treatment of laser physics is left (for the better) to other texts. Laser hazard assessment and safety management are covered in sufficient detail to allow the reader to understand what precautions are necessary to mitigate the risks of laser use. The final section takes a brief look at laser safety in a number of specific industrial applications. These include industrial processing, medicine, telecommunications and entertainment. These should be taken in the context of the second section and are not stand-alone text. With few typographical errors, and packed with practical hints, this book serves as an excellent text for any educational course on laser safety and provides a quick and easy reference for laser safety officers. (book review: A Roy Henderson - ISBN: 0 412 72940 7)

Safety Training: Ergonomie - sensibilisation à l'ergonomie bureautique - French version only

CERN Multimedia

Laetitia Laddada

2004-01-01

Nous vous proposons une 1/2 journée de sensibilisation sur les risques engendrés par une mauvaise posture lors du travail sur écran (mal de dos, fatigue visuelle, douleurs des poignets...) et des bonnes pratiques pour y remédier. Les prochaines sessions auront lieu le 8 juillet 2004. Les cours sont pris en charge par la Commission de Sécurité et animés par Clemente Pilly et Ribordy Marion de « PM postures ». L'inscription via EDH est obligatoire. Pour plus d'information et inscription par EDH à ce cours, veuillez consulter les pages Formation et Développement (groupe sécurité) de HR, ou contacter l'organisateur. Les places seront attribuées dans l'ordre de réception des inscriptions. Organisateur : Ana-Paula Bernardes/SC-GS (71385) Ana-paula.bernardes@cern.ch Formation en SECURITE SAFETY Training Laetitia Laddada 73811 - 79236 safety.training@cern.ch

DOE interpretations Guide to OSH standards. Update to the Guide

Energy Technology Data Exchange (ETDEWEB)

1994-03-31

Reflecting Secretary O`Leary`s focus on occupational safety and health, the Office of Occupational Safety is pleased to provide you with the latest update to the DOE Interpretations Guide to OSH Standards. This Guide was developed in cooperation with the Occupational Safety and Health Administration, which continued it`s support during this last revision by facilitating access to the interpretations found on the OSHA Computerized Information System (OCIS). This March 31, 1994 update contains 123 formal in letter written by OSHA. As a result of the unique requests received by the 1-800 Response Line, this update also contains 38 interpretations developed by DOE. This new occupational safety and health information adds still more important guidance to the four volume reference set that you presently have in your possession.

DOE interpretations Guide to OSH standards. Update to the Guide

Energy Technology Data Exchange (ETDEWEB)

1994-03-31

Reflecting Secretary O`Leary`s focus on occupational safety and health, the Office of Occupational Safety is pleased to provide you with the latest update to the DOE Interpretations Guide to OSH Standards. This Guide was developed in cooperation with the Occupational Safety and Health Administration, which continued its support during this last revision by facilitating access to the interpretations found on the OSHA Computerized Information System (OCIS). This March 31, 1994 update contains 123 formal interpretation letters written by OSHA. As a result of the unique requests received by the 1-800 Response Line, this update also contains 38 interpretations developed by DOE. This new occupational safety and health information adds still more important guidance to the four volume reference set that you presently have in your possession.

DOE interpretations Guide to OSH standards. Update to the Guide

Energy Technology Data Exchange (ETDEWEB)

1994-03-31

Reflecting Secretary O`Leary`s focus on occupational safety and health, the Office of Occupational Safety is pleased to provide you with the latest update to the DOE Interpretations Guide to OSH Standards. This Guide was developed in cooperation with the Occupational Safety and Health Administration, which continued its support during this last revision by facilitating access to the interpretations found on the OSHA Computerized Information System (OCIS). This March 31, 1994 update contains 123 formal interpretation letters written OSHA. As a result of the unique requests received by the 1-800 Response Line, this update also contains 38 interpretations developed by DOE. This new occupational safety and health information adds still more important guidance to the four volume reference set that you presently have in your possession.

Les brulures electriques chez les voleurs de cuivre

Science.gov (United States)

Belmir, R.; Fejjal, N.; Achbouk, H.; El Mazouz, S.; Gharib, N.; Abassi, A.; Belmahi, A.

2011-01-01

Summary Les vols de biens fabriqués avec le cuivre semblent en hausse depuis un certain temps du fait de son prix élevé de revente, ce qui est à l’origine d’une augmentation du nombre d’accidents électriques par haut voltage (AEHV) qui sont graves du fait des brûlures profondes qu’elles provoquent le long des axes vasculo-nerveux. Les Auteurs rapportent une série de neuf cas d’AEHV traités au service de chirurgie plastique et de brûlés de l’Hôpital Ibn Sina de Rabat, Maroc, à travers laquelle ils étudient les caractéristiques épidémiologiques, cliniques et thérapeutiques. La population intéressée était jeune et active. Les brûlures étaient secondaires à un contact avec des câbles à haute tension lors de tentatives de vol par arrachement de conducteurs en cuivre dans les transformateurs dans 67% des cas, et lors de tentatives de coupure de caténaires alimentant les trains électriques sur le réseau ferroviaire dans 33% des cas. Le traitement des lésions électrothermiques a nécessité des interventions itératives avec amputation et désarticulation des segments de membres nécrosés dans 66% des cas, dont les suites étaient marquées par des séquelles fonctionnelles invalidantes. La prévention de ce type d’AEHV reste fondamentale. PMID:22262961

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

Energy Technology Data Exchange (ETDEWEB)

Delage, M; Giroux, C

1990-12-01

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

Les risques du travail

CERN Document Server

Thébaud-Mony, Annie

2015-01-01

Depuis les années 1990, les conditions de travail se sont peu à peu imposées dans le débat social. Néanmoins, la situation reste critique. Les risques traditionnels n'ont pas disparu : les manutentions lourdes, l'exposition professionnelle aux cancérogènes, au bruit ou aux vibrations demeurent répandues... De plus, certaines " améliorations " n'ont fait que déplacer et dissimuler les problèmes, telle l'externalisation des risques grâce à la sous-traitance. Dans le même temps, les transformations du travail et des modalités de gestion de la main-d'œuvre ont fragilisé les collectifs et accru l'isolement des salariés, conduisant à une montée visible de la souffrance psychique. Face à ces évolutions, il est plus que jamais nécessaire que tous les acteurs concernés, en particulier les salariés eux-mêmes et leurs représentants, s'approprient les connaissances indispensables pour améliorer la protection de la santé sur les lieux du travail. Tel est le but de ce livre, qui renouvelle int�...

The protection of labour against radioactivity in French uranium mines; Mesures prises dans les mines d'uranium de France pour assurer la protection du personnel contre les dangers de la radioactivite

Energy Technology Data Exchange (ETDEWEB)

Avril, R; Berger, Ch; Duhamel, F; Pradel, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1958-07-01

The exploration and working of radioactive mineral deposits expose those concerned to both external and internal irradiation. Special protective measures are therefore required. In French mines, systematic monitoring and the observation of safety rules are applied effectively in combating irradiation risk. The preventive measures, however, considerably affect the manner of working and consequently boost the cost of the ore. (author) [French] Les travaux de recherches et d'exploitation executes dans les gisements de substances radioactives exposent le personnel des irradiations internes et externes necessitant des mesures speciales de protection. Dans les mines fran ises, un controle systematique des conditions de travail permet de mener de fa n efficace la lutte contre ces irradiations en respectant certaines normes de securite. Les mesures de prevention ont des repercussions sensibles sur la conduite de l'exploitation et, par suite, sur le prix de revient du minerai extrait. (auteur)

Comment scolariser les enfants Roms? Les enfants Roms dans les dispositifs mis en place à Bordeaux Métropole.

OpenAIRE

Øhlund, Ida

2016-01-01

Dans ce mémoire, je m intéresse à la scolarisation des enfants Roms en France. Je présente la place des enfants Roms dans la scolarisation en Europe et en France. Je discute les efforts qu on fait en France pour scolariser ces enfants, et je prends comme exemple les mesures d intégration prises par les autorités de Bordeaux Métropole en expliquant les rôles des différents acteurs locaux. Dans la première partie, j essaye de présenter le groupe minoritaire européen appelé « Rom ». J aborde l h...

Management of waste from the use of radioactive material in medicine, industry, agriculture, research and education safety guide

CERN Document Server

2005-01-01

This Safety Guide provides recommendations and guidance on the > fulfilment of the safety requirements established in Safety Standards > Series No. WS-R-2, Predisposal Management of Radioactive Waste, > Including Decommissioning. It covers the roles and responsibilities of > different bodies involved in the predisposal management of radioactive > waste and in the handling and processing of radioactive material. It > is intended for organizations generating and handling radioactive > waste or handling such waste on a centralized basis for and the > regulatory body responsible for regulating such activities.  > Contents: 1. Introduction; 2. Protection of human health and the > environment; 3. Roles and responsibilities; 4. General safety > considerations; 5. Predisposal management of radioactive waste; 6. > Acceptance of radioactive waste in disposal facilities; 7. Record > keeping and reporting; 8. Management systems; Appendix I: Fault > schedule for safety assessment and environmental impact assessment; > Ap...

Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material (2012 Ed.). Specific Safety Guide

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-06-15

This Safety Guide provides recommendations and guidance on achieving and demonstrating compliance with IAEA Safety Standards Series No. SSR-6, Regulations for the Safe Transport of Radioactive Material (2012 Edition), which establishes the requirements to be applied to the national and international transport of radioactive material. Transport is deemed to comprise all operations and conditions associated with and involved in the movement of radioactive material, including the design, fabrication and maintenance of packaging, and the preparation, consigning, handling, carriage, storage in transit and receipt at the final destination of packages. This publication supersedes IAEA Safety Standards Series No. TS-G-1.1 Rev. 1, which was issued in 2008.

Formation sécurité : places disponibles dans les sessions de juin

CERN Multimedia

DGS Unit

2010-01-01

Il reste des places dans les formations sécurité suivantes. Pour les mises à jour et les inscriptions, veuillez vous reportez au catalogue des formations sécurité. Safety in Cryogenics level 1, 14 juin, en anglais, 3 heures, 9h00 – 12h00 (5 places) Radiological Protection, 18 juin, en anglais, 4 heures, 13h30 – 17h30 (15 places) Radiological Protection, 22 juin, en anglais, 4 heures, 08h30 – 12h30 (15 places) Sécurité Radiologique, 22 juin, en français, 4 heures, 13h30 – 17h30 (15 places) Conduite de chariots élévateurs, 24-25 juin, en français, 2 jours, 8h00 – 17h30 (3 places) 

Territorialisation et enclaves littorales dans les îles de la Caraïbe

Directory of Open Access Journals (Sweden)

Michel Desse

2008-04-01

Full Text Available Les littoraux de la Caraïbe ont longtemps été considérés comme des espaces de l’envers, ouverts, libres, propriété de l’Etat donc de tous, opposables à la plantation qui hiérarchise la société, structure le paysage et identifie la richesse.Aujourd’hui, les littoraux constituent les centres fonctionnels des îles, annexés parfois privatisés, ils apparaissent fortement territorialisés. Les facteurs qui expliquent ces transformations sont multiples. Les îles connaissent une forte tertiairisation ...

Les pressions écologiques réglementaires : comment les entreprises tunisiennes les gèrent-elles ?

Directory of Open Access Journals (Sweden)

Ahmed Turki

2012-06-01

Full Text Available Les entreprises sont de plus en plus appelées aujourd’hui à prendre en considération les aspects environnementaux dans leur gestion. Elles sont la cible des pressions environnementales dont la principale source est les pouvoirs publics. Ainsi, le présent papier se propose d’étudier la nature de la relation entre les entreprises et les pouvoirs publics en matière de protection de l’environnement. Afin d’atteindre cet objectif, une étude de cas est effectuée sur 8 entreprises tunisiennes dont deux sont certifiées par la norme ISO 14001. Les résultats montrent que toutes les entreprises ont fait l’objet d’inspections périodiques et de pénalités de la part des pouvoirs publics qui constituent la principale et parfois l’unique source de pression environnementale dans le contexte tunisien. Ces entreprises trouvent que les normes législatives environnementales sont difficiles à atteindre. Aussi, les résultats identifient deux types de relations entre les entreprises et les pouvoirs publics : coopérative et conflictuelle. De même, l’étude de cas montre que les pressions environnementales ont diminué suite aux actions environnementales effectuées mais demeurent toujours présentes.Companies are today more and more called to consider the ecological aspects in their management. They are the target of the ecological pressures the main source of which is public authorities. So, the present paper suggests studying the nature of the relation between companies and public authorities in environmental protection. To reach this objective, a case study is made on 8 Tunisian companies among which two are certified to the standard ISO 14001. The results show that public authorities (constitute the most and sometimes the only source of ecological pressure in the Tunisian context. These pressures show themselves by overhauls and penalties. These companies find that the environmental legislative standards are difficult to achieve

N° 341-Diagnostic et prise en charge de la torsion annexielle chez les filles, les adolescentes et les femmes adultes.

Science.gov (United States)

Kives, Sari; Gascon, Suzy; Dubuc, Élise; Van Eyk, Nancy

2017-02-01

Passer en revue les connaissances scientifiques actuelles et formuler des recommandations relatives au diagnostic et à la prise en charge de la torsion annexielle chez les filles, les adolescentes et les femmes adultes. L'étude porte sur les facteurs de risque, la précision diagnostique, les options de prise en charge et les issues de la torsion annexielle. RéSULTATS: Nous avons examiné les études publiées en faisant des recherches dans MEDLINE, Embase, CINAHL et la Bibliothèque Cochrane à l'aide d'une terminologie contrôlée et de mots-clés appropriés (« adnexal torsion », « ovarian torsion »). Nous avons limité les résultats aux revues systématiques, aux essais contrôlés aléatoires, aux essais cliniques contrôlés et aux études d'observation. Nous avons refait les recherches de façon régulière et intégré de nouvelles données à la directive jusqu'en décembre 2014. Nous avons également étudié la littérature grise (non publiée) trouvée sur les sites Web d'organismes d'évaluation des technologies de la santé et d'autres organismes connexes, dans des collections de directives cliniques et dans des registres d'essais cliniques, et obtenue auprès d'associations nationales et internationales de médecins spécialistes. Les résultats ont été examinés et évalués par le comité CANPAGO de la Société des obstétriciens et gynécologues du Canada (SOGC), sous la direction des auteures principales. Les recommandations ont été classées selon les critères établis par le Groupe d'étude canadien sur les soins de santé préventifs. AVANTAGES, DéSAVANTAGES ET COûTS: L'application de la directive devrait aider les praticiens à adopter une approche de diagnostic et de prise en charge optimale en matière de torsion annexielle, à réduire au minimum les effets néfastes et à améliorer l'issue qui attend les patientes. La présente directive a été évaluée et approuvée par le Comité de pratique - gynécologie de la SOGC

Safety system status monitoring

International Nuclear Information System (INIS)

Lewis, J.R.; Morgenstern, M.H.; Rideout, T.H.; Cowley, P.J.

1984-03-01

The Pacific Northwest Laboratory has studied the safety aspects of monitoring the preoperational status of safety systems in nuclear power plants. The goals of the study were to assess for the NRC the effectiveness of current monitoring systems and procedures, to develop near-term guidelines for reducing human errors associated with monitoring safety system status, and to recommend a regulatory position on this issue. A review of safety system status monitoring practices indicated that current systems and procedures do not adequately aid control room operators in monitoring safety system status. This is true even of some systems and procedures installed to meet existing regulatory guidelines (Regulatory Guide 1.47). In consequence, this report suggests acceptance criteria for meeting the functional requirements of an adequate system for monitoring safety system status. Also suggested are near-term guidelines that could reduce the likelihood of human errors in specific, high-priority status monitoring tasks. It is recommended that (1) Regulatory Guide 1.47 be revised to address these acceptance criteria, and (2) the revised Regulatory Guide 1.47 be applied to all plants, including those built since the issuance of the original Regulatory Guide

Safety system status monitoring

Energy Technology Data Exchange (ETDEWEB)

Lewis, J.R.; Morgenstern, M.H.; Rideout, T.H.; Cowley, P.J.

1984-03-01

The Pacific Northwest Laboratory has studied the safety aspects of monitoring the preoperational status of safety systems in nuclear power plants. The goals of the study were to assess for the NRC the effectiveness of current monitoring systems and procedures, to develop near-term guidelines for reducing human errors associated with monitoring safety system status, and to recommend a regulatory position on this issue. A review of safety system status monitoring practices indicated that current systems and procedures do not adequately aid control room operators in monitoring safety system status. This is true even of some systems and procedures installed to meet existing regulatory guidelines (Regulatory Guide 1.47). In consequence, this report suggests acceptance criteria for meeting the functional requirements of an adequate system for monitoring safety system status. Also suggested are near-term guidelines that could reduce the likelihood of human errors in specific, high-priority status monitoring tasks. It is recommended that (1) Regulatory Guide 1.47 be revised to address these acceptance criteria, and (2) the revised Regulatory Guide 1.47 be applied to all plants, including those built since the issuance of the original Regulatory Guide.

Les trous noirs

CERN Document Server

Ioli, Elena

2016-01-01

L'univers est peuplé par des étoiles, des planètes, des galaxies, des astéroïdes, des comètes, mais les trous noirs en sont certainement les habitants les plus mystérieux et les plus fascinants ! Grâce à cette merveilleuse histoire racontée par papy Gino, professeur d'astronomie, les trous noirs n auront plus de secrets pour vous ! C est l'été, le soleil illumine le ciel, la plage est en feu : une journée à la plage pleine de jeux et de plongée qui va se transformer pour Bernardo, Gregorio et leurs deux amis en une aventure inattendue. Ils découvriront les secrets des trous noirs, d étranges objets célestes que personne n'a jamais vus mais qui existent bel et bien ! Grand-père Gino, un professeur d astronomie à la retraite, emmènera les enfants à l'intérieur d'un trou noir, leur expliquera pourquoi ils sont noirs, comment ils sont nés et comment les scientifiques pensent qu'ils vont mourir. Et Gino leur racontera même ce qui se trouve de l'autre côté d'un trou noir...

Les bourses du CRDI appuient les futurs chefs de file dans le ...

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

13 mai 2015 ... Un programme de bourses de recherche du CRDI appuie les recherches novatrices et renforce le leadership futur et les connaissances sur les TIC, les ... Internet, la radio communautaire et la vidéo participative, présentent un fort potentiel pour faire face aux répercussions des changements climatiques et ...

Inegalites entre les garçons et les filles dans l'evaluation en ...

African Journals Online (AJOL)

Cette recherche se propose d'étudier les inégalités entre les garçons et les filles dans l'évaluation en Education Physique et Sportive dans les collèges et surtout de connaître leurs sentiments par vis-à-vis de cette évaluation. Cette étude aura pour cadre les établissements secondaires de Porto-Novo et environs.

Diagnostic feasibility and safety of CT-guided core biopsy for lung nodules less than or equal to 8 mm. A single-institution experience

Energy Technology Data Exchange (ETDEWEB)

Chang, Ying-Yueh [Taipei Veterans General Hospital, Department of Radiology, Taipei (China); Chen, Chun-Ku [Taipei Veterans General Hospital, Department of Radiology, Taipei (China); National Yang-Ming University, School of Medicine, Taipei (China); National Yang-Ming University, Institute of Clinical Medicine, Taipei (China); Yeh, Yi-Chen [National Yang-Ming University, School of Medicine, Taipei (China); Taipei Veterans General Hospital, Department of Pathology and Laboratory Medicine, Taipei (China); Wu, Mei-Han [Taipei Veterans General Hospital, Department of Radiology, Taipei (China); National Yang-Ming University, School of Medicine, Taipei (China)

2018-02-15

This retrospective study evaluated the diagnostic yield and safety of CT-guided core biopsy of pulmonary nodules ≤8 mm. We determined the diagnostic yield and safety profile of CT-guided lung biopsies for 125 pulmonary nodules ≤8 mm. Pathological diagnoses were made by a combination of histopathological examination and imprint cytology. Results were compared with biopsy results for 134 pulmonary nodules >8 and ≤10 mm. Final diagnoses were established in 94 nodules ≤8 mm. The sensitivity, specificity and diagnostic accuracy of CT-guided core biopsy for nodules ≤8 mm were 87.1 % (61/70 nodules), 100 % (24/24) and 90.4 % (85/94), respectively. Diagnostic failure rates were comparable for nodules ≤8 mm and nodules >8 mm and ≤10 mm (9/94, 9.6 % and 7/111, 6.3 %, respectively, P=0.385). The rate of tube thoracostomy for nodules ≤8 mm was comparable to that for nodules >8 and ≤10 mm (1.6 % vs. 0.7 %, P=0.611). Nodules ≤6 mm had a higher non-diagnostic result rate of 15.4 % (6/39) than did nodules >8 and ≤10 mm (3.7 %, 5/134, P=0.017). CT-guided pulmonary biopsy is feasible for lung nodules ≤8 mm, especially those >6 mm, and has an acceptable diagnostic yield and safety profile. (orig.)

Engineering design guidelines for nuclear criticality safety

International Nuclear Information System (INIS)

Waltz, W.R.

1988-08-01

This document provides general engineering design guidelines specific to nuclear criticality safety for a facility where the potential for a criticality accident exists. The guide is applicable to the design of new SRP/SRL facilities and to major modifications Of existing facilities. The document is intended an: A guide for persons actively engaged in the design process. A resource document for persons charged with design review for adequacy relative to criticality safety. A resource document for facility operating personnel. The guide defines six basic criticality safety design objectives and provides information to assist in accomplishing each objective. The guide in intended to supplement the design requirements relating to criticality safety contained in applicable Department of Energy (DOE) documents. The scope of the guide is limited to engineering design guidelines associated with criticality safety and does not include other areas of the design process, such as: criticality safety analytical methods and modeling, nor requirements for control of the design process

Les Fintech sont-elles une opportunité ou une menace pour les banques traditionnelles ?

OpenAIRE

Blanc, Aldwin; Sonney, Frédéric

2018-01-01

Dans ce travail, nous étudierons les potentielles opportunités et menaces que sont les Fintech pour les institutions bancaires. Cela nous permettra de savoir si, à l’avenir, ces entreprises vont s’imposer et remplacer les banques telles que nous les connaissons ou alors aider, forcer les acteurs traditionnels à effectuer leur révolution numérique pour répondre aux nouvelles attentes des clients. Afin de répondre à cette interrogation, les trois strates de l’environnement bancaire ont été anal...

Autres modèles de prestation de services publics dans les ...

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

Les écrits sur la prestation de services publics à l'aide de modèles différents ont porté jusqu'à maintenant sur des endroits très précis. Ils ont par ailleurs été circonscrits à des secteurs donnés et ont manqué d'uniformité sur le plan méthodologique. Ce projet vise à analyser les modèles de prestation de services de santé, ...

Yield and Safety Profile of Ultrasound Guided Fine Needle Aspiration Cytology (FNAC) of Lymph Nodes

International Nuclear Information System (INIS)

Sattar, A.; Wahab, S.; Javed, A.; Shamim, S. H.

2016-01-01

Objective: To determine the re-biopsy rate, positive yield and safety profile of ultrasound guided fine needle aspiration cytology (FNAC) in cervical lymph nodes in terms of its complications and repeat procedures. Study Design: An analytical study. Place and Duration of Study: Department of Vascular and Interventional Radiology, Dow University Hospital, Dow University of Health Sciences, Karachi, from June to December 2013. Methodology: Eighty neck swellings, which were found to be lymph nodes on ultrasound, underwent ultrasound guided FNAC, from outpatients. Lymph nodes which were included in the study were those that were not easily palpable, located near major blood vessels, where patient refused of direct palpation and wanted image guided FNAC, those directly sent by physician for image guided FNAC and where blind biopsy remained inconclusive. Patients who refused on explanation or did not give consent were excluded. Complications and repeat biopsy were noted. Result: This study consisted of 80 cases, of which 51 cases (63.75 percentage) were female and 29 cases (36.25 percentage) were male. Repeat biopsy was required in 1 case (1.6 percentage). There were no procedure-related complications. A total of 44 cases (55 percentage) revealed evidence suggesting or confirming the existence of tuberculosis. Rest of the others showed other benign lesions, reactive lymphadenopathy and malignancy. Conclusion: Ultrasound guided FNAC is a safe procedure with low re-biopsy rate that aids diagnosis. The predominant cause of cervical lymphadenopathy in this study was tuberculous lymphadenitis. (author)

Safety functions and component classification for BWR, PWR and PTR

International Nuclear Information System (INIS)

1979-01-01

The Safety Guide forms part of the IAEA programme, referred to as the NUSS programme (Nuclear Safety Standards), for establishing Codes of Practice and Safety Guides relating to thermal neutron power plants. The present Safety Guide has the following chapters: safety functions, ranking of safety functions, assignment of safety class requirements. Design requirements for structural integrity of boundaries of fluid-retaining components are also discussed

Les adjectifs à valeur intensive dans les groupes nominaux

Directory of Open Access Journals (Sweden)

Buvet Pierre-André

2012-07-01

Full Text Available Un dictionnaire électronique est élaboré dans la perspective du Traitement Automatique des Langues. Il s'agit d'une ressource qui est exploité par un ensemble d'outils informatiques pour donner lieu à une application dédiée au traitement de l'information textuelle. Le dictionnaire électronique présenté dans l'article concerne principalement des adjectifs prédicatifs à forme simple qui ont fait l’objet d’un recensement exhaustif et qui ont été décrits formellement. Sa macrostructure est constituée de plus de 20 000 emplois adjectivaux. Sa microstructure comporte des descripteurs normalisés de telle sorte que les informations métalinguistiques stipulées permettent d'effectuer des analyses sémantiques fines. Les adjectifs prédicatifs à forme complexe sont également incorporés au dictionnaire; ils sont décrits comme les adjectifs prédicatifs à forme simple dans la mesure où ils fonctionnent de la même façon. Dans un premier temps, nous discutons de la notion d'adjectif prédicatif en précisant préalablement les notions de prédicat et d'emploi prédicatif ainsi que celles de signification lexicale et de signification grammaticale. Nous présentons les marqueurs de l’intensité qui correspondent à des adjectifs monolexicaux et prédicatifs ou bien polylexicaux et prédicatifs. Nous discutons de ces adjectifs dans un premier temps selon qu’il s’agit de modifieurs libres, dans un deuxième temps de modifieurs liés et dans un troisième temps de constituants d’une détermination figée. Nous précisons dans les trois cas de figure quelles sont les conditions d’occurrences des adjectifs prédicatifs dans les groupes nominaux en nous appuyant sur les descriptions des adjectifs et des déterminants du français qui proviennent de deux bases de données exhaustives.

The management system for the safe transport of radioactive material. Safety guide

International Nuclear Information System (INIS)

2008-01-01

The purpose of this Safety Guide is to provide information to organizations that are developing, implementing or assessing a management system for activities relating to the transport of radioactive material. Such activities include, but are not limited to, design, fabrication, inspection and testing, maintenance, transport and disposal of radioactive material packaging. This publication is intended to assist those establishing or improving a management system to integrate safety, health, environmental, security, quality and economic elements to ensure that safety is properly taken into account in all activities of the organization. Contents: 1. Introduction; 2. Management system; 3. Management responsibility; 4. Resource management; 5. Process implementation; 6. Measurement, assessment and improvement; Appendix: Graded approach for management systems for the safe transport of radioactive materials; Annex I: Two examples of management systems; Annex II: Examples of management system standards; Annex III: Example of a documented management system (or quality assurance programme) for an infrequent consignor; Annex IV: Example of a documented management system (or quality assurance programme) description for an infrequent carrier; Annex V: Example of a procedure for control of records; Annex VI: Example of a procedure for handling packages containing radioactive materials, including receipt and dispatch; Annex VII: Example of a packaging maintenance procedure in a complex organization; Annex VIII: Example of an internal audit procedure in a small organization; Annex IX: Example of a corrective and preventive action procedure

[Efficacy and safety of ultrasound-guided or neurostimulator-guided bilateral axillary brachial plexus block].

Science.gov (United States)

Xu, C S; Zhao, X L; Zhou, H B; Qu, Z J; Yang, Q G; Wang, H J; Wang, G

2017-10-17

Objective: To explore the efficacy and safety of bilateral axillary brachial plexus block under the guidance of ultrasound or neurostimulator. Methods: From February 2012 to April 2014, 120 patients undergoing bilateral hand/forearm surgery in Beijing Jishuitan Hospital were enrolled and anaesthetized with bilateral axillary brachial plexus block. All patients were divided into two groups randomly using random number table: the ultrasound-guided group (group U, n =60) and the neurostimulator-guidedgroup (group N, n =60). The block was performed with 0.5% ropivacaine. Patients' age, sex and operation duration were recorded. Moreover, success rate, performance time, onset of sensor and motor block, performance pain, patient satisfaction degree and the incidence of related complications were also documented. Venous samples were collected at selected time points and the total and the plasma concentrations of ropivacaine were analyzed with HPLC. Results: The performance time, the onset of sensor block and the onset of motor block of group U were (8.2±1.5), (14.2± 2.2)and (24.0±3.5)min respectively, which were markedly shorter than those in group N( (14.6±3.9), (19.9±3.8), (28.8±4.2)min, respectively), and the differences were statistically significant( t =11.74, 10.09, 6.73, respectively, all P 0.05). No analgesic was superadded and no other anesthesia methods were applied. No complications were detected perioperatively. Conclusions: The bilateral axillary brachial plexus block under the guidance of ultrasound or neurostimulator are both effective and safe for bilateral hand/forearm surgery. However, the ultrasound-guided block may be more clinically beneficial because of its shorter performance time, rapid onset and higher patient satisfaction degree.

Les lieux du sacré dans les Miracula sancti Germani d’Heiric d’Auxerre et les Gesta pontificum Autissiodorensium

Directory of Open Access Journals (Sweden)

Dominique Iogna-Prat

2004-09-01

Full Text Available Comment cerner la notion de sacré dans les textes carolingiens que sont les Gestes des évêques d’Auxerre et les Miracles de saint Germain écrits par l’un des maîtres de l’école carolingienne d’Auxerre, Heiric ? Une étude lexicale précise des mots latins employés par les auteurs permet d’approcher au plus près les concepts renvoyant aux lieux du sacré. Ce sujet de maîtrise. suggéré par D. Iogna-Prat et réalisé sous la direction de M. Bourin (université de Paris I-Panthéon Sorbonne, avec l’aid...

Ethnobotanique des plantes médicinales chez les bergers peuls de ...

African Journals Online (AJOL)

Objectif: Le savoir indigène à Widou Thiengoly est entre les mains des bergers qui vivent dans des écosystèmes souvent fragilisés. Il est normal de préserver ce savoir nomade et ancestral. Méthodologie et résultats: Ainsi, nous avons mené des enquêtes auprès des bergers peuls de Widou. Un guide d'entretien a été ...

A Safety and Health Guide for Vocational Educators. Incorporating Requirements of the Occupational Safety and Health Act of 1970, Relevant Pennsylvania Requirements with Particular Emphasis for Those Concerned with Cooperative Education and Work Study Programs. Volume 15. Number 1.

Science.gov (United States)

Wahl, Ray

Intended as a guide for vocational educators to incorporate the requirements of the Occupational Safety and Health Act (1970) and the requirements of various Pennsylvania safety and health regulations with their cooperative vocational programs, the first chapter of this document presents the legal implications of these safety and health…

Les catastrophes naturelles présentent une menace pour les ...

African Journals Online (AJOL)

toufik

L'événement sismique a été simulé en utilisant le catalogue algérien des failles actives. Les résultats obtenus montrent que les constructions les plus endommagées sont celles qui reposent sur des sols meubles. Mots-clés : SIG, risque sismique, probabilité de dommages, courbes de fragilité, Hazus. Abstract. Use of a GIS ...

Writer`s guide for technical procedures

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-12-01

A primary objective of operations conducted in the US Department of Energy (DOE) complex is safety. Procedures are a critical element of maintaining a safety envelope to ensure safe facility operation. This DOE Writer`s Guide for Technical Procedures addresses the content, format, and style of technical procedures that prescribe production, operation of equipment and facilities, and maintenance activities. The DOE Writer`s Guide for Management Control Procedures and DOE Writer`s Guide for Emergency and Alarm Response Procedures are being developed to assist writers in developing nontechnical procedures. DOE is providing this guide to assist writers across the DOE complex in producing accurate, complete, and usable procedures that promote safe and efficient operations that comply with DOE orders, including DOE Order 5480.19, Conduct of Operations for DOE Facilities, and 5480.6, Safety of Department of Energy-Owned Nuclear Reactors.

Les stratégies des investisseurs : des bords de ville aux bords de mer

Directory of Open Access Journals (Sweden)

Sophie Cueille

2004-03-01

Full Text Available L’architecture de la villégiature a un prix. Construire des villes nouvelles, qu’elles soient balnéaires, thermales ou périurbaines, induit la mise en place de réseaux ferroviaires et viaires, d’édifices dévolus à la détente, les soins ou les jeux, d’hôtels et de maisons. Quels sont les investisseurs qui engagent d’importants financements en ces lieux ? Personnages de la vie politique, industrielle et bancaire, le plus souvent parisiens, tous se saisissent des besoins de la nouvelle société bourgeoise montante, consommatrice de loisirs dès le milieu du XIXe siècle. Si certains projets peuvent être initialement teintés d’une certaine forme de philanthropie, toutes les opérations deviennent très vite de véritables entreprises lucratives. Sociétés civiles en tous genres, concessions et affermages, les formules d’investissement s’adaptent au produit où souvent se mêlent intérêts publics et privés. La réussite de tels projets suscite également le financement de campagnes publicitaires importantes : journaux, affiches et guides sont publiés pour faire accourir la clientèle visée et ainsi rapporter aux investisseurs les profits escomptés.

Outline of examination guides of water-cooled research reactors in Japan

International Nuclear Information System (INIS)

Yoshino, F.; Kimura, R.

1992-01-01

The Nuclear Safety Commission of Japan published two examination guides of water-cooled research reactors on July 18, 1991; one is for safety design, and another is for safety evaluation. In these guides, careful consideration is taken into account on the basic safety characteristic features of research reactors in order to be reasonable regulative requirements. This paper describes the fundamental philosophy and outline of the guides. (author)

Deterministic Safety Analysis for Nuclear Power Plants. Specific Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2012-01-01

The IAEA's Statute authorizes the Agency to establish safety standards to protect health and minimize danger to life and property - standards which the IAEA must use in its own operations, and which a State can apply by means of its regulatory provisions for nuclear and radiation safety. A comprehensive body of safety standards under regular review, together with the IAEA's assistance in their application, has become a key element in a global safety regime. In the mid-1990s, a major overhaul of the IAEA's safety standards programme was initiated, with a revised oversight committee structure and a systematic approach to updating the entire corpus of standards. The new standards that have resulted are of a high calibre and reflect best practices in Member States. With the assistance of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its safety standards. Safety standards are only effective, however, if they are properly applied in practice. The IAEA's safety services - which range in scope from engineering safety, operational safety, and radiation, transport and waste safety to regulatory matters and safety culture in organizations - assist Member States in applying the standards and appraise their effectiveness. These safety services enable valuable insights to be shared and I continue to urge all Member States to make use of them. Regulating nuclear and radiation safety is a national responsibility, and many Member States have decided to adopt the IAEA's safety standards for use in their national regulations. For the contracting parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions. The standards are also applied by designers, manufacturers and operators around the world to enhance nuclear and radiation safety in power generation, medicine, industry, agriculture, research and education

Safety Training: Ergonomie - Sensibilisation à l'ergonomie bureautique

CERN Multimedia

2004-01-01

If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an "application for training" form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt. SAFETY TRAINING Laetitia Laddada tel. 73811 - 79236 safety.training@cern.ch Nous vous proposons une 1/2 journée de sensibilisation sur les risques engendrés par une mauvaise posture lors du travail sur écran (mal de dos, fatigue visuelle, douleurs des poignets...) et des bonnes pratiques pour y remédier. Les prochaines sessions auront lieu le 11 mars 2004. Les cours sont pris en charge par la Commission de Sécurité et animés par Clemente Pilly et Ribordy Marion de « PM postures...

Nonreactor nuclear facilities: standards and criteria guide

International Nuclear Information System (INIS)

Brynda, W.J.; Junker, L.; Karol, R.C.; Lobner, P.R.; Goldman, L.A.

1981-09-01

This guide is a source document that identifies standards, codes, and guides that address the nuclear safety considerations pertinent to nuclear facilities as defined in DOE Order 5480.1, Chapter V, Safety of Nuclear Facilities. The guidance and criteria provided are directed toward areas of safety usually addressed in a Safety Analysis Report. The areas of safety include, but are not limited to, siting, principal design criteria and safety system design guidelines, radiation protection, accident analysis, and quality assurance. The guide is divided into two sections: general guidelines and appendices. Those guidelines that are broadly applicable to most nuclear facilities are presented in the general guidelines. These general guidelines may have limited applicability to subsurface facilities such as waste repositories. Guidelines specific to the various types or categories of nuclear facilities are presented in the appendices. These facility-specific appendices provide guidelines and identify standards and criteria that should be considered in addition to, or in lieu of, the general guidelines

Nonreactor nuclear facilities: Standards and criteria guide

International Nuclear Information System (INIS)

Brynda, W.J.; Scarlett, C.H.; Tanguay, G.E.; Lobner, P.R.

1986-09-01

This guide is a source document that identifies standards, codes, and guides that address the nuclear safety considerations pertinent to nuclear facilities as defined in DOE 5480.1A, Chapter V, ''Safety of Nuclear Facilities.'' The guidance and criteria provided is directed toward areas of safety usually addressed in a Safety Analysis Report. The areas of safety include, but are not limited to, siting, principal design criteria and safety system design guidelines, radiation protection, accident analysis, conduct of operations, and quality assurance. The guide is divided into two sections: general guidelines and appendices. Those guidelines that are broadly applicable to most nuclear facilities are presented in the general guidelines. Guidelines specific to the various types or categories of nuclear facilities are presented in the appendices. These facility-specific appendices provide guidelines and identify standards and criteria that should be considered in addition to, or in lieu of, the general guidelines. 25 figs., 62 tabs

Regulations and guides for nuclear power plants

International Nuclear Information System (INIS)

1984-01-01

The purpose of the present Guide is to provide information, guidance and recommendations to assist the regulatory body of a Member State in establishing its own regulations and guides. It discusses the purpose, the method and procedure of establishment, and the content and legal status of these documents, and it explains how to use the Codes of Practice and Safety Guides issued by the IAEA under the Nuclear Safety Standards (NUSS) programme. Certain aspects of how to use other international standards and appropriate regulations and guides from other countries are discussed

Prise en charge de l’infection gonococcique chez les adultes et les jeunes

Science.gov (United States)

Pogany, Lisa; Romanowski, Barbara; Robinson, Joan; Gale-Rowe, Margaret; Latham-Carmanico, Cathy; Weir, Christine; Wong, Tom

2015-01-01

Résumé Objectif Présenter des recommandations sur la prise en charge de l’infection gonococcique chez les adultes et les jeunes. Qualité des données Les recommandations thérapeutiques des lignes directrices canadiennes sur les infections transmissibles sexuellement reposent sur une recherche documentaire de même que sur des catégories de recommandations et des niveaux de qualité de données déterminés par au moins 2 évaluateurs. Les recommandations ont été revues par des pairs et sont en instance d’approbation par le groupe de travail d’experts. Message principal Les nouvelles recommandations portant sur la prise en charge de l’infection gonococcique chez les adultes et les jeunes préconisent les cultures à titre d’outil diagnostique lorsqu’elles sont pratiques, le traitement par antibiothérapie combinée (ceftriaxone associée à l’azithromycine) et le signalement sans délai de tous les cas dont le traitement a échoué aux autorités de santé publique. Conclusion Si elles sont suivies, ces nouvelles recommandations pourraient réduire l’échec thérapeutique, contribuer à une surveillance plus étroite des tendances à la résistance de Neisseria gonorrhoeae aux antibiotiques et contribuer à prévenir la transmission de gonorrhée résistante à plusieurs médicaments.

Faut-il brûler les dictionnaires ? Ou comment les ressources numériques ont révolutionné les recherches en morphologie

Directory of Open Access Journals (Sweden)

Namer Fiammetta

2012-07-01

Full Text Available Pour mener leurs études, les morphologues, et, singulièrement parmi eux, ceux qui traitent du lexique construit, sont pris entre deux tensions : utiliser les données issues des dictionnaires, réputées fiables parce que passées au travers du crible de l’institutionnalisation, ou se fonder sur des données authentiques, produites dans des situations écologiques. Bien qu’inspirant encore de la défiance, le Web devient alors la ressource par excellence. Les ressources numérisées telles que les archives de journaux ou les bases de données de textes littéraires constituent un moyen terme entre ces deux pratiques : elles permettent d’effectuer des recherches basées sur l’usage, tout en offrant la garantie d’une certaine tenue linguistique de la part des scripteurs, la plupart du temps identifiables. Dans cette communication, nous nous demanderons si les dictionnaires méritent la confiance que continuent de leur octroyer les morphologues ou, plus exactement, si une morphologie qui puise ses données dans les seuls dictionnaires peut encore avoir cours au 21e siècle. Pour engager cette discussion, nous commencerons par poser la question de l’existence, pour un lexème construit. Nous exposerons ensuite ce que constitue une morphologie basée sur l’usage, puis donnerons un aperçu des types de recherches que permettent de réaliser les ressources non dictionnairiques. La conclusion sera que, si les dictionnaires continuent d'avoir droit de cité dans la panoplie du morphologue, une morphologie uniquement basée sur les données qu'ils contiennent passerait outre de nombreuses recherches, plus fructueuses les unes que les autres.

Safety Assessment for Research Reactors and Preparation of the Safety Analysis Report. Specific Safety Guide

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-11-15

The IAEA's Statute authorizes the Agency to 'establish or adopt' standards of safety for protection of health and minimization of danger to life and property' - standards that the IAEA must use in its own operations, and which States can apply by means of their regulatory provisions for nuclear and radiation safety. The IAEA does this in consultation with the competent organs of the United Nations and with the specialized agencies concerned. A comprehensive set of high quality standards under regular review is a key element of a stable and sustainable global safety regime, as is the IAEA's assistance in their application. The IAEA commenced its safety standards programme in 1958. The emphasis placed on quality, fitness for purpose and continuous improvement has led to the widespread use of the IAEA standards throughout the world. The Safety Standards Series now includes unified Fundamental Safety Principles, which represent an international consensus on what must constitute a high level of protection and safety. With the strong support of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its standards. Standards are only effective if they are properly applied in practice. The IAEA's safety services encompass design, siting and engineering safety, operational safety, radiation safety, safe transport of radioactive material and safe management of radioactive waste, as well as governmental organization, regulatory matters and safety culture in organizations. These safety services assist Member States in the application of the standards and enable valuable experience and insights to be shared. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA's standards for use in their national regulations. For parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions

Safety Assessment for Research Reactors and Preparation of the Safety Analysis Report. Specific Safety Guide

International Nuclear Information System (INIS)

2011-01-01

The IAEA's Statute authorizes the Agency to 'establish or adopt' standards of safety for protection of health and minimization of danger to life and property' - standards that the IAEA must use in its own operations, and which States can apply by means of their regulatory provisions for nuclear and radiation safety. The IAEA does this in consultation with the competent organs of the United Nations and with the specialized agencies concerned. A comprehensive set of high quality standards under regular review is a key element of a stable and sustainable global safety regime, as is the IAEA's assistance in their application. The IAEA commenced its safety standards programme in 1958. The emphasis placed on quality, fitness for purpose and continuous improvement has led to the widespread use of the IAEA standards throughout the world. The Safety Standards Series now includes unified Fundamental Safety Principles, which represent an international consensus on what must constitute a high level of protection and safety. With the strong support of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its standards. Standards are only effective if they are properly applied in practice. The IAEA's safety services encompass design, siting and engineering safety, operational safety, radiation safety, safe transport of radioactive material and safe management of radioactive waste, as well as governmental organization, regulatory matters and safety culture in organizations. These safety services assist Member States in the application of the standards and enable valuable experience and insights to be shared. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA's standards for use in their national regulations. For parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions

Wastes in Aquitaine. A regional guide; Les dechets en Aquitaine. Guide regional

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-04-01

In the framework of French environmental policy and municipal and industrial waste disposal programs, a guide is presented for the Aquitaine region, which gives a comprehensive information on waste disposal effects and waste processing. Waste types and associated regulations are presented, with emphasis on volumes and data for Aquitaine region, followed by information on the various environmental labels and waste collection procedures, processing and ultimate disposal systems, financial incentives and taxes, waste exchange systems... The various types of municipal, industrial, agricultural and food industry wastes are reviewed with information on their characteristics, volumes, legislation, collection, processing and upgrading, and disposal

Gradients socioéconomiques du risque cardiovasculaire chez les enfants et les adolescents canadiens

Directory of Open Access Journals (Sweden)

Y. Shi

2016-01-01

Full Text Available Introduction : Les maladies cardiovasculaires (MCV et leurs facteurs de risque présentent des gradients socioéconomiques clairs chez les adultes canadiens, mais présentent des ambiguïtés chez les enfants. L'objectif de cette étude est de vérifier l'existence ou non de gradients socioéconomiques dans les marqueurs physiologiques du risque de MCV chez les enfants et les adolescents canadiens. Méthodologie : À partir des données transversales combinées de l'Enquête canadienne sur les mesures de la santé 2007-2011, nous avons étudié, chez 2 149 enfants (6 à 11 ans et 2 073 adolescents (12 à 17 ans et selon le sexe, les marqueurs de risque cardiovasculaire suivants : excès de poids (y compris l'obésité, score de capacité aérobique (SCA, pression artérielle (PA, lipides sanguins (totaux, cholestérol LDL et HDL, triglycérides, métabolisme du glucose et protéine C réactive (CRP. Des analyses de régression logistique et de régression linéaire multidimensionnelles ont permis de dégager les tendances relatives au risque cardiovasculaire en fonction de la suffisance du revenu du ménage et du niveau de scolarité des parents, après ajustement en fonction de l'âge et de l'origine ethnique, et après stratification par groupe d'âge et par sexe. Résultats : La prévalence de l'obésité était sensiblement plus élevée chez les jeunes garçons que chez les jeunes filles (prévalence de 18,5 %, intervalle de confiance [IC] à 95 % : 15,6 à 21,5 contre 7,7 %, IC à 95 % : 5,2 à 10,3. Toutefois, des gradients socioéconomiques négatifs ont été observés en ce qui concerne le risque d'adiposité chez les jeunes filles et les adolescentes, et non chez les garçons. Parmi les enfants et les adolescents, les garçons étaient en meilleure condition physique que les filles (SCA moyen de 541, IC à 95 % : 534 à 546 contre 501, IC à 95 % : 498 à 505 chez les enfants; 522, IC à 95 % : 514 à 529 contre 460, IC à 95 % : 454

Jeux chez les Touaregs

OpenAIRE

Bernus, E.

2012-01-01

Parmi les jeux pratiqués par les Touaregs, il faut distinguer les jeux sportifs qui opposent deux équipes ou deux hommes, des jeux de société dans un cadre inscrit dans le sable, et les jeux d’esprit, véritables joutes verbales ; enfin, il faut signaler la construction par les enfants de jouets. Un certain nombre de jeux sont connus chez d’autres populations africaines. L’ouvrage de Charles Béart, Jeux et jouets de l’Ouest africain (1955), nous permet d’utiles comparaisons. Il est donc intére...

Methods of supervision in the uranium industry; Les methodes de controle dans l'industrie de l'uranium

Energy Technology Data Exchange (ETDEWEB)

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

1961-07-01

In its broad sense the supervision applied to uranium refining is not appreciably different from that found in ordinary industry. It should be noted however that the main preoccupation will be exceptional purity in the final product, and constant vigilance must be directed towards conforming with the accepted safety standards in such an organisation. The various problems at issue and the steps taken to solve them will be discussed successively. (author) [French] L'aspect general du controle dans le raffinage de l'uranium ne differe pas sensiblement de celui que l'on peut rencontrer dans les industries classiques. Il conviendra cependant de remarquer que le souci dominant visera plus a l'obtention d'un produit final de purete exceptionnelle et qu'une vigilance de tous les instants sera necessaire pour respecter les normes de securite dans une telle entreprise. On etudiera successivement les divers objectifs a atteindre et l'organisation mise en oeuvre pour les realiser. (auteur)

Safety and Efficacy of Ultrasound-Guided Fiducial Marker Implantation for CyberKnife Radiation Therapy

Energy Technology Data Exchange (ETDEWEB)

Kim, Jae Hyun; Hong, Seong; Sook; Kim, Jung Hoon; Park, Hyun Jeong; Chang, Yun Woo; Chang, A Ram [Soonchunhyang University Seoul Hospital, Seoul (Korea, Republic of); Kwon, Seok Beom [Hallym University College of Medicine, Chuncheon (Korea, Republic of)

2012-06-15

To evaluate the safety and technical success rate of an ultrasound-guided fiducial marker implantation in preparation for CyberKnife radiation therapy. We retrospectively reviewed 270 percutaneous ultrasound-guided fiducial marker implantations in 77 patients, which were performed from June 2008 through March 2011. Of 270 implantations, 104 were implanted in metastatic lymph nodes, 96 were in the liver, 39 were in the pancreas, and 31 were in the prostate. During and after the implantation, major and minor procedure-related complications were documented. We defined technical success as the implantation enabling adequate treatment planning and CT simulation. The major and minor complication rates were 1% and 21%, respectively. One patient who had an implantation in the liver suffered severe abdominal pain, biloma, and pleural effusion, which were considered as major complication. Abdominal pain was the most common complication in 11 patients (14%). Among nine patients who had markers inserted in the prostate, one had transient hematuria for less than 24 hours, and the other experienced transient voiding difficulty. Of the 270 implantations, 261 were successful (97%). The reasons for unsuccessful implantations included migration of fiducial markers (five implantations, 2%) and failure to discriminate the fiducial markers (three implantations, 1%). Among the unsuccessful implantation cases, six patients required additional procedures (8%). The symptomatic complications following ultrasound-guided percutaneous implantation of fiducial markers are relatively low. However, careful consideration of the relatively higher rate of migration and discrimination failure is needed when performing ultrasound-guided percutaneous implantations of fiducial markers.

Association entre les hormones sexuelles, les marqueurs de ...

African Journals Online (AJOL)

Introduction: Le présent travail se propose d'étudier la relation entre les hormones sexuelles, notamment l'oestradiol et l'indice de l'oestradiol libre, le sulfate de déhydroépiandrosterone et la sex hormone binding globulin, les marqueurs de remodelage osseux et la densité minérale osseuse chez une population de ...

Guiding principles for the implementation of non-animal safety assessment approaches for cosmetics: skin sensitisation.

Science.gov (United States)

Goebel, Carsten; Aeby, Pierre; Ade, Nadège; Alépée, Nathalie; Aptula, Aynur; Araki, Daisuke; Dufour, Eric; Gilmour, Nicola; Hibatallah, Jalila; Keller, Detlef; Kern, Petra; Kirst, Annette; Marrec-Fairley, Monique; Maxwell, Gavin; Rowland, Joanna; Safford, Bob; Schellauf, Florian; Schepky, Andreas; Seaman, Chris; Teichert, Thomas; Tessier, Nicolas; Teissier, Silvia; Weltzien, Hans Ulrich; Winkler, Petra; Scheel, Julia

2012-06-01

Characterisation of skin sensitisation potential is a key endpoint for the safety assessment of cosmetic ingredients especially when significant dermal exposure to an ingredient is expected. At present the mouse local lymph node assay (LLNA) remains the 'gold standard' test method for this purpose however non-animal test methods are under development that aim to replace the need for new animal test data. COLIPA (the European Cosmetics Association) funds an extensive programme of skin sensitisation research, method development and method evaluation and helped coordinate the early evaluation of the three test methods currently undergoing pre-validation. In May 2010, a COLIPA scientific meeting was held to analyse to what extent skin sensitisation safety assessments for cosmetic ingredients can be made in the absence of animal data. In order to propose guiding principles for the application and further development of non-animal safety assessment strategies it was evaluated how and when non-animal test methods, predictions based on physico-chemical properties (including in silico tools), threshold concepts and weight-of-evidence based hazard characterisation could be used to enable safety decisions. Generation and assessment of potency information from alternative tools which at present is predominantly derived from the LLNA is considered the future key research area. Copyright © 2012 Elsevier Inc. All rights reserved.

Martine Grinberg. Écrire les coutumes. Les droits seigneuriaux en France

Directory of Open Access Journals (Sweden)

Maïté Lesné-Ferret

2009-05-01

Full Text Available L’auteur observe tout ce qu’a entraîné la mise par écrit des coutumes, toutes les interventions qui illustrent une clarification ou une modification de la pensée juridique. Les développements sont répartis en trois parties : après une description des droits seigneuriaux (p. 9 à 60, l’étude s’attache au travail d’interprétation mené par les juristes sur le droit coutumier, en particulier sur les droits féodaux – « Ecrire le droit. Le chantier des juristes » (p. 63 à 133 – et souligne le rapp...

Consensus standards utilized and implemented for nuclear criticality safety in Japan

International Nuclear Information System (INIS)

Nomura, Yasushi; Okuno, Hiroshi; Naito, Yoshitaka

1996-01-01

The fundamental framework for the criticality safety of nuclear fuel facilities regulations is, in many advanced countries, generally formulated so that technical standards or handbook data are utilized to support the licensing safety review and to implement its guidelines. In Japan also, adequacy of the safety design of nuclear fuel facilities is checked and reviewed on the basis of licensing safety review guides. These guides are, first, open-quotes The Basic Guides for Licensing Safety Review of Nuclear Fuel Facilities,close quotes and as its subsidiaries, open-quotes The Uranium Fuel Fabrication Facility Licensing Safety Review Guidesclose quotes and open-quotes The Reprocessing Facility Licensing Safety Review Guides.close quotes The open-quotes Nuclear Criticality Safety Handbook close-quote of Japan and the Technical Data Collection are published and utilized to supply related data and information for the licensing safety review, such as for the Rokkasho reprocessing plant. The well-established technical standards and data abroad such as those by the American Nuclear Society and the American National Standards Institute are also utilized to complement the standards in Japan. The basic principles of criticality safety control for nuclear fuel facilities in Japan are duly stipulated in the aforementioned basic guides as follows: 1. Guide 10: Criticality control for a single unit; 2. Guide 11: Criticality control for multiple units; 3. Guide 12: Consideration for a criticality accident

Radiation safety in X-ray facilities

International Nuclear Information System (INIS)

2001-09-01

The guide specifies the radiation safety requirements for structural shielding and other safety arrangements used in X-ray facilities in medical and veterinary X-ray activities and in industry, research and education. The guide is also applicable to premises in which X-ray equipment intended for radiation therapy and operating at a voltage of less than 25 kV is used. The guide applies to new X-ray facilities in which X-ray equipment that has been used elsewhere is transferred. The radiation safety requirements for radiation therapy X-ray devices operating at a voltage exceeding 25 kV, and for the premices in which such devices are used, are set out in Guide ST 2.2

Radiation safety in X-ray facilities

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-09-01

The guide specifies the radiation safety requirements for structural shielding and other safety arrangements used in X-ray facilities in medical and veterinary X-ray activities and in industry, research and education. The guide is also applicable to premises in which X-ray equipment intended for radiation therapy and operating at a voltage of less than 25 kV is used. The guide applies to new X-ray facilities in which X-ray equipment that has been used elsewhere is transferred. The radiation safety requirements for radiation therapy X-ray devices operating at a voltage exceeding 25 kV, and for the premices in which such devices are used, are set out in Guide ST 2.2.

Communiquer ! les bibliothécaires, les décideurs et les journalistes

CERN Document Server

2010-01-01

L'enjeu de la communication en direction des élus, des décideurs, mais aussi des journalistes, est devenu vital pour les bibliothèques : il s'agit de donner à voir aux tutelles leurs activités, de rendre intelligible leur stratégie de développement, de construire une image institutionnelle forte. De quels moyens dispose la bibliothèque pour faire la preuve du bien-fondé de son existence ? Comment communiquer en direction d'un élu municipal ou régional, d'un responsable politique de la bibliothèque ? Que peut apporter une bonne collaboration avec des journalistes, avec les partenaires naturels ou hiérarchiques au sein de l'université ou de la collectivité territoriale ? Comment utiliser à bon escient les méthodes du lobbying et du marketing, ou l'emploi des réseaux sociaux ? Voilà quelques-unes des questions abordées ici.

Packaging review guide for reviewing safety analysis reports for packagings: Revision 0

International Nuclear Information System (INIS)

Fischer, L.E.; Chou, C.K.; Lloyd, W.R.; Mount, M.E.; Nelson, T.A.; Schwartz, M.W.; Witte, M.C.

1987-09-01

The Department of Energy (DOE) has established procedures for obtaining certification of packagings used by DOE and its contractors for the transport of radioactive materials. These certification review policies and procedures are established to ensure that DOE packaging designs and operations meet safety criteria at least equivalent to the standards prescribed by the Nuclear Regulatory Commission (NRC) certification process for packaging. The Packaging Review Guide (PRG) is not a DOE order, but has been prepared as guidance for the Packaging Certification Staff (PCS) under the Certifying Official, Office of Security Evaluations, or designated representatives. The principal purpose of the PRG is to assure the quality and uniformity of PCS reviews, and to present a well-defined base from which to evaluate proposed changes in the scope and requirements of reviews. The PRG also sets forth solutions and approaches determined to be acceptable in the past by the PCS in dealing with a specific safety issue or safety-related design area. These solutions and approaches are presented in this form so that reviewers can take consistent and well-understood positions as the same safety issues arise in future cases. An applicant submitting a SARP does not have to follow the solutions or approaches presented in the PRG. However, applicants should recognize that the PCS has spent substantial time and effort in reviewing and developing their positions for the issues. A corresponding amount of time and effort will probably be required to review and accept new or different solutions and approaches. Finally, it is also a purpose of the PRG to make information about DOE certification policy and procedures widely available to DOE field offices, DOE contractors, federal agencies, and interested members of the public. 7 refs., 15 figs., 14 tabs

Espaces, formes et enjeux identitaires dans Les petits-fils nègres de Vercingétorix de A. Mabanckou

Directory of Open Access Journals (Sweden)

Katrien Snoeck

2017-02-01

Full Text Available Dans l’œuvre romanesque de A. Mabanckou, le roman Les petits-fils nègres de Vercingétorix occupe une place particulière. Avec sobriété, l’auteur guide la plume de son héroïne, Hortense Iloki, pour peindre la violence aveugle à laquelle les hommes de son pays, le Viétongo, en proie à leurs démons identitaires, se livrent sans retenue. Tandis que la guerre civile fait rage, les femmes résistent à la haine tribale, s’organisent même pour témoigner de l’horreur dont elles sont les premières victimes. Viétongo ou Congo ? Ce qui se veut fictionnel rejoint la brutale réalité de la guerre civile de 1997 au Congo Brazzaville. En dénonçant l’instrumentalisation de questions identitaires par des hommes politiques africains à des fins personnelles, ce roman inscrit son auteur parmi les grands romanciers engagés de la sous-région.

Les changements climatiques et l'urbanisation menacent les ...

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

5 sept. 2014 ... Cette perception correspond-elle aux données scientifiques ? Shah Alam Khan. Dans les quatre villes étudiées, on observe effectivement de réels changements dans les précipitations annuelles, mais pas nécessairement une diminution. À Gurgaon, il y aurait diminution selon l'opinion générale, ce qui ...

Nuclear safety regulations

International Nuclear Information System (INIS)

1998-01-01

The Departmental Rules and The Safety Guides were issued by the NNSA in 1998. The NNSA performed the activities of propagation and implementation of nuclear safety regulations at QTNPP in order to improve the nuclear safety culture of operating organization and construct and contract organizations

Le Pétrole et les dispersants dans les mers baignant le littoral canadien: évaluation des recherches et recommandations

National Research Council Canada - National Science Library

Sprague, John B; Vandermeulen, J. H; Wells, P. G; Birchard, E. C

1982-01-01

...; les methodes d'analyse; les effets du petrole, des dispersants et du petrole disperse chimiquement sur le phytoplancton, les macrophytes, le zooplancton, les poissons, les organismes et animaux benthiques et intertidaux, les oiseaux, les mammiferes marins, les communautes et les ecosystemes. Il comporte certaines recommandations en vue de recherches futures indispensables et donne des conseils sur la facon de minimiser les effets de deversements de petrole dans le milieu marin canadien.

Teaching Competencies for the Online Environment | Enseigner les compétences pour l’environnement en ligne

Directory of Open Access Journals (Sweden)

Heather Marie Farmer

2016-08-01

Full Text Available The goals of this study are to identify key competency areas that lead to success in online instruction and to develop a framework that supports professional development and self-assessment. To identify the key competency areas, skills and behaviours presented within current literature were analyzed. Secondly, gaps were identified and levels of competence were determined within each key competency area. The resulting analysis produced the Online Teaching Competency (OTC Matrix including five competency areas: Community & Netiquette, Active Teaching/Facilitating, Instructional Design, Tools & Technology, and Leadership & Instruction. This leveled competency matrix can be used to inform professional development in the online teaching environment and is also a useful guide in the areas of self-assessment, portfolio design, and the development and evaluation of professional development opportunities. Cette étude a comme objectifs de cerner les principaux domaines de compétences qui mènent à la réussite de l’instruction en ligne et de développer un cadre qui soutient le développement professionnel et l’autoévaluation. Afin de cerner les principaux domaines de compétences, une analyse des aptitudes et comportements présentés dans les études actuelles a été réalisée. Deuxièmement, les écueils ont été cernés et les niveaux de compétence ont été déterminés au sein de chaque domaine de compétences. L’analyse qui en a résulté a généré la matrice des compétences de l’enseignement en ligne, comprenant cinq domaines de compétences : collectivité et nétiquette, enseignement actif/animation active, conception de l’instruction, outils et technologie, ainsi que leadership et instruction. Cette matrice graduée peut servir à façonner le développement professionnel dans un environnement d’enseignement en ligne. Elle sert aussi de guide pratique pour les domaines de l’auto-évaluation, de la conception de

Drafting Lab Management Guide.

Science.gov (United States)

Ohio State Univ., Columbus. Instructional Materials Lab.

This manual was developed to guide drafting instructors and vocational supervisors in sequencing laboratory instruction and controlling the flow of work for a 2-year machine trades training program. The first part of the guide provides information on program management (program description, safety concerns, academic issues, implementation…

Arizona Traffic Safety Education, K-8. Passenger Safety, Grade 3.

Science.gov (United States)

Mesa Public Schools, AZ.

One in a series designed to assist Arizona elementary and junior high school teachers in developing children's traffic safety skills, this curriculum guide contains four lessons and an appendix of school bus safety tips for use in grade 3. Introductory information provided for the teacher includes basic highway safety concepts, stressing…

Les tribunaux, et non pas les liens de parenté, offrent de meilleures ...

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

29 janv. 2018 ... Les recherches menées au Bangladesh et en Inde ont révélé que les femmes et les personnes provenant de populations marginalisées ont besoin de tribunaux qui fonctionnent bien pour exploiter leur plein potentiel.

Les Malalties dels cereals

OpenAIRE

Puiggrós i Jové, Josep Maria

1989-01-01

En aquest treball es fa una descripció de les principals malalties dels cereals que han estat trobades a Catalunya. Agrupant-les segons ataquin la fulla i espiga: oïdi, rovells, septòries, Rhynchosporium, Helminthosporium, i virus; al coll i tija: Cercosporella, Ophiobolus, Rhizoctbnia i Fusarium o bé les que vénen de la llavor: carbons, càries i Helminthospbrium. A part de la descripció, hom fa esment de les observacions efectuades els darrers anys en els diferents indrets de...

Les souvenirs du fondateur

Directory of Open Access Journals (Sweden)

Marie-Thérèse Curie

2009-11-01

Full Text Available J’étais vicaire à Notre-Dame de Dole dans les années cinquante. Cette fonction, à cette époque, me mettait en contact permanent avec les mouvements de jeunesse, ceux de l’âge d’or des « patros » et des colonies de vacances. On me demanda d’ailleurs de créer plusieurs de ces « colos » de filles (La Rixouse, les Rivières, les Perrets dans le Jura, mais aussi à l’île d’Yeu pour le diocèse. Mon bon contact avec les jeunes et la confiance de ma hiérarchie me désignèrent pour m’occuper d’une paroi...

Les gens, et non les choses, calment les eaux de la lagune de Tam ...

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

Cathy Egan

La lagune de Tam Giang au Viet Nam est un habitat naturel presque parfait pour la pêche et l'aquaculture. Longue de plus de 70 km et d'une profondeur moyenne d'à peine deux mètres, la lagune est un milieu des plus productifs, tant pour les espèces d'eau douce que pour les espèces marines. Au cours des dernières ...

Document de travail 6: A Conceptual Framework to Guide Research ...

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

16 déc. 2010 ... Document de travail 6: A Conceptual Framework to Guide Research on ... du secteur privé ainsi que les tendances qui influencent l'élaboration et la ... afin de guider l'élaboration de son agenda de recherche en matière de ...

Des agriculteurs déterminent les innovations et les pratiques qui ...

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

16 sept. 2013 ... Les chercheurs ont constaté que les agriculteurs préféraient des cultures de valeur élevée telles que le mil et le sorgho au maïs, car elles se vendent à meilleur prix et résistent mieux à la sécheresse. Les agriculteurs apprécient tout particulièrement le sorgho gadam parce qu'il existe déjà un client local, ...

Gènere i TIC: el procés d’autoinclusió de les dones en les TIC. Una aproximació des de les tecnòlogues artístiques i les tecnòlogues informàtiques

OpenAIRE

Vergés Bosch, Núria

2012-01-01

En aquesta tesi s'analitza el procés d'autoinclusió de les dones en les TIC, entès com una estratègia on les dones se situen com agents conductores de la seva pròpia inclusió TIC. Per una banda, té per objectiu explorar la relació gènere i TIC. Per altra banda, conèixer les estratègies d'autoinclusió, és a dir, les principals motivacions, possibilitadors i mecanismes d'autoinclusió que hi intervenen. Finalment, es busca comparar aquestes qüestions per a les tecnòlogues artístiques i les tecnò...

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

Development approach on usage of radiation and inspection of QA according to the change of approval procedure of safety regulatory guides

International Nuclear Information System (INIS)

Oh, B. J.; Ahn, H. Z.; Kim, S. W.; Yoo, S. O.; Kang, S. C.; Yang, S. H.; Han, S. J.; Kim, H. S.; Kim, H. J.

2002-01-01

In accordance with 2001 amendment of the Atomic Energy Act(AEA), KINS also amended its internal 'Regulation on Implementation of Entrusted AEA-related Work'. Up to now the nuclear safety-specialized institute has used its internally developed guidelines in the safety regulation. From now on, however, the institute will enhance the objectivity and transparency by having the instruments approved by the Ministry of Science ad Technology. In this paper, we introduced the major points and directions to be considered to the development of the safety regulatory guides on Inspection for the quality assurance of the nuclear reactor facilities and the use of radioisotopes, and review and inspection for dosimeter reading

Aldicarbe et crimidine dans les eaux et les sédiments aux alentours ...

African Journals Online (AJOL)

homme et de l'environnement, sont utilisées contre les pestes et autres nuisibles. Cependant, la plupart des études menées se sont focalisées sur les organochlorés. La fréquence de détection et les concentrations des pesticides aldicarbe et ...

Stratégies fondées sur les citoyens - collaboration avec les ...

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

Dans le cadre de ce projet, on cherchera à comprendre le climat d'insécurité au sein des collectivités touchées par la violence à Medellín, en Colombie, du point de vue de ceux qui le vivent (les populations vulnérables). Travaillant de concert avec des membres de la collectivité, les chercheurs relèveront les principaux ...

Les dyslipidemies et antiretroviraux chez les personnes vivant avec ...

African Journals Online (AJOL)

hypercholestérolémie, l'hyper LDL-cholestérolémie, l'hypo HDLcholestérolémie ont été retrouvées respectivement chez 41,4%, 23,5% et 17,4% des patients. La différence n'est pas significative entre les fréquences des troubles lipidiques chez les ...

Rural expressway intersection safety toolbox : desktop reference.

Science.gov (United States)

2011-06-01

This document is intended to be a guide for planning-level decisions concerning safety : issues and subsequent potential improvements at rural expressway intersections. It is : NOT a design guide. It simply presents the gamut of safety treatment opti...

Les institutions de recherche sur les politiques et les ODD liés à la ...

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

Le nouveau site Web facilitera l'enregistrement des événements démographiques afin d'améliorer l'accès aux services pour tous. Le nouveau site Web et la nouvelle bibliothèque de ressources aideront à améliorer les systèmes d'information et d'enregistrement des faits d'état civil dans les pays en développement.

Anàlisi de les modificacions estatutàries per adaptar el règim de reemborsament del capital social a les normes comptables de les cooperatives

Directory of Open Access Journals (Sweden)

Yolanda Montegut

2014-12-01

Full Text Available Objecte: L’objectiu del treball és analitzar les modificacions realitzades en els Estatuts de les cooperatives per adaptar el capital social a les normes comptables i veure quins han estats els efectes econòmics de l’adaptació del capital social en la situació patrimonial i econòmica de les cooperatives. Disseny/metodologia: Per dur a terme l’estudi s’ha demanat al Registre de Cooperatives  els Estatuts i els comptes anuals, per al període 2010-2011, de les cooperatives objecte de l’estudi. En primer lloc s’han revisat els Estatuts per veure quins articles han modificat o han introduït en relació a la nova normativa comptable. En segon lloc s’ha creat una base de dades amb els comptes anuals de les cooperatives per tal d’analitzar la situació econòmica i financera de les mateixes a través d’un anàlisi de les masses del balanç i de ràtios. Aportacions i resultats: S’ha identificat el percentatge de cooperatives que han decidit adaptar els Estatuts a la reforma comptable i el criteri adoptat per les mateixes. Els resultats mostren que les cooperatives han adaptat majoritàriament els seus Estatuts i que els efectes de l’aplicació de les normes comptables adaptades a la NIC 32 consisteixen en una disminució del patrimoni net i un augment de l’endeutament. Limitacions: La dificultat temporal per anar obtenint els comptes anuals i els Estatuts de les diferents cooperatives existents a Catalunya. Implicacions pràctiques i socials: Degut a que des de 2011 totes les cooperatives espanyoles han d'aplicar les normes comptables adaptades a la NIC 32, els resultats d'aquest treball de recerca poden ser útils per a diferents grups d'interès, no solament per a les pròpies cooperatives, sinó també per altres organismes cooperatius per a què puguin realitzar les valoracions que creguin convenients i per a les entitats financeres, per tal que puguin tenir-los en compte a l'hora de prendre decisions. Valor afegit

Les faits,une arme contre

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

les anime. Les villages avoisinants s'en inspirent : neuf d'entre eux ont demandé des conseils pour aménager des potagers. Selon les habitants de Lilbouré, les autres veulent suivre leur exemple. Mais, rappelle leur porte-parole, le progrès a un coût : il faut s'organiser, participer aux réunions, verser ses cotisations, tenir ...

Accroître l'inclusion financière pour les femmes et les jeunes ...

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

Accroître l'inclusion financière pour les femmes et les jeunes vulnérables : Proyecto Capital. L'accès à des services financiers officiels peut aider les personnes les plus pauvres du monde à échapper à la pauvreté et à réduire leur vulnérabilité. Ce projet aidera à accroître la sécurité économique de femmes et de jeunes ...

Les outils du CERN

CERN Multimedia

1999-01-01

C'est le plus grand centre mondial de recherche en physique des particules. Les outils du Laboratoire, accélérateurs et détecteurs de particules, figurent parmi les instruments scientifiques les plus complexes au monde. Des prix Nobels ont d'ailleurs été attribués aux physiciens du CERN pour leurs développements.

Quines empreses han aguantat millor la crisi, les empreses familiars o les no familiars?

Directory of Open Access Journals (Sweden)

Jose Luis Gallizo

2014-12-01

Full Text Available Objecte: En aquest estudi és porta a terme un anàlisi comparatiu sobre l’evolució de l’estructura econòmica i financera que presenten les empreses familiars i no familiars de Catalunya en un context d’intensa crisi econòmica. La seva finalitat és poder donar resposta a dos qüestions principals: identificar les característiques diferencials de l’EF respecte a l’EnF i comprovar si aquestes característiques diferencials han permès a les EF aguantar millor la crisi econòmica. Disseny/metodologia: S’ha analitzat una mostra de 750 grans i mitjanes empreses de Catalunya (550 familiars i 200 no familiars durant el període 2008-2012. Les dades s’han obtingut a través de la base de dades SABI, i per a la classificació de les empreses en familiars i no familiars s’ha dut a terme una comprovació individual de cadascuna d’elles per evitar habituals errors de classificació. Posteriorment les empreses s’han classificat en funció de la seva dimensió per dotar d’una major robustes els resultats. També s’ha procurat que la distribució d’empreses per sectors fos similar en les diferents categories per evitar que un efecte sectorial pogués tergiversar els resultats de l’estudi. Aportacions i resultats: L’estudi ha permès constatar les hipòtesis establertes sobre el finançament de les empreses familiars i concloure que aquestes presenten una estructura financera diferent a les Empreses no familiars. Les empreses familiars als seus balanços, presenten un major nivell d’autofinançament gràcies a la seva menor distribució de dividends. A més a més, les EF presenten millors resultats en quant a nivells de cobertura i liquiditat, ja que es troben més capitalitzades i presenten uns nivells d’endeutament inferior que les Empreses no familiars. Aquestes característiques patrimonials i financeres han contribuït a que les empreses familiars aguantin millor els anys de crisi, produint-se durant aquests anys

30 CFR 57.19019 - Guide ropes.

Science.gov (United States)

2010-07-01

... Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR METAL AND NONMETAL MINE SAFETY AND HEALTH SAFETY AND HEALTH STANDARDS-UNDERGROUND METAL AND NONMETAL MINES Personnel Hoisting Wire Ropes... than shaft development, the nominal strength (manufacturer's published catalog strength) of the guide...

Safety Education Resources: Childproofing Your Home

Science.gov (United States)

... Kids and Babies En Español Kids and Babies - Safety Alerts Back to Safety Education Resources Air Mattresses ... Home Drowning Deaths in Spanish Kids and Babies - Safety Guides Back to Safety Education Resources Baby Safety ...

Diagnostic accuracy and safety of CT-guided fine needle aspiration biopsy in cavitary pulmonary lesions

Energy Technology Data Exchange (ETDEWEB)

Zhuang, Yi-Ping, E-mail: yipingzhuang2010@sina.com [Department of Radiology, Jiangsu Cancer Institute and Hospital, No. 42 Baiziting Road, Nanjing 210009, Jiangsu (China); Wang, Hai-Yan, E-mail: mycherishgirl@sohu.com [Department of Radiology, Jiangsu Cancer Institute and Hospital, No. 42 Baiziting Road, Nanjing 210009, Jiangsu (China); Zhang, Jin, E-mail: yari_zj@hotmail.com [Department of Radiology, Jiangsu Cancer Institute and Hospital, No. 42 Baiziting Road, Nanjing 210009, Jiangsu (China); Feng, Yong, E-mail: fengyong119@sohu.com [Department of Radiology, Jiangsu Cancer Institute and Hospital, No. 42 Baiziting Road, Nanjing 210009, Jiangsu (China); Zhang, Lei, E-mail: motozl163@163.com [Department of Radiology, Jiangsu Cancer Institute and Hospital, No. 42 Baiziting Road, Nanjing 210009, Jiangsu (China)

2013-01-15

Objective: CT-guided transthoracic biopsy is a well-established method in the cytologic or histologic diagnosis of pulmonary lesions. The knowledge of its diagnostic performance and complications for cavitary pulmonary lesions is limited. The purpose of this study was to determine the diagnostic accuracy and safety of CT-guided fine needle aspiration biopsy (FNAB) in cavitary pulmonary lesions. Materials and methods: 102 consecutive patients with pulmonary cavitary lesions received CT-guided FNAB with use of an 18-gauge (n = 35) or 20-gauge (n = 67) Chiba for histology diagnosis. The sensitivity, specificity, and diagnostic accuracy of FNAB were calculated as compared with the final diagnosis. Complications associated with FNAB were observed. The diagnostic accuracy and complications were compared between patients with different lesion sizes and different cavity wall thickness. Results: The overall sensitivity, specificity, and accuracy of FNAB were 96.3%, 98.0%, and 96.1%, respectively. The sensitivity, specificity, and diagnosis accuracy in different lesion size (<2 cm vs ≥2 cm), or different cavity wall thickness (<5 mm vs ≥5 mm) were not different (P > 0.05; 0.235). More nondiagnostic sample was found in wall thickness <5 mm lesions (P = 0.017). Associated complications included pneumothorax in 9 (8.8%) patients and alveolar hemorrhage in 14 patients (13.7%) and hemoptysis in 1 patient (1%). No different rate of complications was found with regard to lesion size, wall thickness, length of the needle path and needle size (P > 0.05). Conclusion: CT-guided FNAB can be effectively ad safely used for patients with pulmonary cavitary lesions.

L'INNOVATION DANS LES SERVICES : DES MODALITÉS ORIGINALES, QUI PEUVENT ENRICHIR LES CONCEPTIONS INDUSTRIELLES

OpenAIRE

Gadrey , Jean; Gallouj , Faïz; Weinstein , Olivier

1995-01-01

International audience; Bien qu'ils soient largement majoritaires dans les grands agrégats économiques, les théories économiques de l'innovation tendent à négliger les services ou à considérer que l'innovation y est pour l'essentiel réduite à l'adoption d'innovations produites dans l'industrie. Dans cette contribution, on conteste ces points de vue en examinant les trois questions suivantes -pourquoi l'innovation dans les services est-elle méconnue ou oubliée par ces théories? -quelles sont (...

Developing guidance in the nuclear criticality safety assessment for fuel cycle facilities

International Nuclear Information System (INIS)

Galet, C.; Evo, S.

2012-01-01

In this poster IRSN (Institute for radiation protection and nuclear safety) presents its safety guides whose purpose is to transmit the safety assessment know-how to any 'junior' staff or even to give a view of the safety approach on the overall risks to any staff member. IRSN has written a first version of such a safety guide for fuel cycle facilities and laboratories. It is organized into several chapters: some refer to types of assessments, others concern the types of risks. Currently, this guide contains 13 chapters and each chapter consists of three parts. In parallel to the development of criticality chapter of this guide, the IRSN criticality department has developed a nuclear criticality safety guide. It follows the structure of the three parts fore-mentioned, but it presents a more detailed first part and integrates, in the third part, the experience feedback collected on nuclear facilities. The nuclear criticality safety guide is online on the IRSN's web site

La perception enfantine des rôles de sexe : quelles différences avec les adultes

OpenAIRE

Tostain, Manuel; Le Breuilly, Joëlle

2005-01-01

International audience; Dans cette recherche, nous avons étudié les liens entre tolérance à la transgression des rôles de sexe et explications de l'origine des différences entre sexes. Les sujets, des enfants de 7-8 ans et des adultes (des étudiants), devaient évaluer des transgressions de rôles de sexe réalisées par des hommes et par des femmes, puis se positionner au regard des explications biologiques, sociales ou personnelles des différences entre sexes. Les résultats montrent que :1) les...

Planning and preparing for emergency response to transport accidents involving radioactive material. Safety guide

International Nuclear Information System (INIS)

2005-01-01

The objective of this Safety Guide is to provide guidance to the public authorities and others (including consignors, carriers and emergency response authorities) who are responsible for developing and establishing emergency arrangements for dealing effectively and safely with transport accidents involving radioactive material. It may assist those concerned with establishing the capability to respond to such transport emergencies. It provides guidance for those Member States whose involvement with radioactive material is just beginning. It also provides guidance for those Member States that have already developed their radioactive material industries and the attendant emergency plans but that may need to review and improve these plans

De meilleures données probantes sur les dons privés dans les ...

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

... mesurer l'ampleur, les sources et les réussites de la philanthropie ainsi que les facteurs qui la favorisent. ... et futures grâce à son vaste réseau de partenaires individuels et institutionnels. ... Framework Agreement between IISD and IDRC.

Intégrer les sexospécificités dans les politiques macroéconomiques ...

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

28 janv. 2011 ... Produit national brut (PNB), investissement, épargne, balance des paiements — voilà les catégories que les macroéconomistes analysent. Mais l'analyse macroéconomique peut-elle être indifférente aux sexospécificités ? Les économistes ont longtemps considéré que les marchés étaient simplement des ...

Les attaques des Termites (Isoptera) dans les parcelles de ...

African Journals Online (AJOL)

SARAH

31 août 2016 ... habitations, les agro systèmes et les pâturages dans une savane sahélienne à Matam. (Sénégal). Mémoire de DEA, Université Ch. A. Diop de Dakar, pp. 51. Silvestri F : 1914-15. Contribuzione alla conoscenza dei. Termitidi e Termitophili dell'Africa occidentale. I. Termitidi. Bolletino del Laboratorio di ...

Periodic safety review of operational nuclear power plants. A publication within the NUSS programme

International Nuclear Information System (INIS)

1994-01-01

This Safety Guide which supplements the IAEA Safety Fundamentals: The Safety of Nuclear Installations and the Code on the Safety of Nuclear Power Plants: Operation, forms part of the Agency's programme, referred to as the NUSS programme, for establishing Codes and Guides relating to nuclear power plants. A list of NUSS publications is given at the end of this book. This Guide was drafted on the basis of a systematic review approach that was endorsed by the IAEA Conference on the Safety of Nuclear Power: Strategy for the Future. The purpose of this Safety Guide is to provide guidance on the conduct of Periodic Safety Reviews (PSRs) for an operational nuclear power plant. The Guide is directed at both owners/operators and regulators. This Safety Guide deals with the PSR of an operational nuclear power plant. A PSR is a comprehensive safety review addressing all important aspects of safety, carried out at regular intervals. 22 refs, 4 figs

Safety guide of the Tandar accelerator

International Nuclear Information System (INIS)

1987-01-01

The safety standards that the installations of the Tandar accelerator have to comply with are presented here. In order to maintain the safety, the knowledge and the accomplishment of these standards are mandatory for all persons. The risks of external irradiation and of contamination are pointed out. The risks at the Tandar are: the calibration standards used at the premises and the irradiation produced by the activity of the accelerator, which can be primary, secondary, induced or X rays. The identification of the different areas of installation are given with their corresponding classification; the rules concerning the manipulation of radioactive materials and the movement of persons in areas of reglamentary access are established. Finally conventional safety and rules for evacuation and fires are presented. (M.E.L.) [es

Les formes de la séparation dans les Lettres Persanes

Directory of Open Access Journals (Sweden)

Thaïs Chauvel

2017-12-01

Full Text Available Cet article aborde la thématique de la séparation dans le dispositif romanesque des Lettres persanes, de Montesquieu, à savoir, le roman du sérail. De ce fait, cette étude entend analyser les formes de la séparation qui apparaissent dans les lettres des trois personnages membres du sérail: les femmes, leur mari Usbek, ainsi que les gardiens eunuques. En premier lieu, il importe de comprendre dans quelle mesure la forme épistolaire des Lettres persanes implique la séparation. Par la suite, on analysera d’abord la réaction des épouses face au départ de leur mari dans les lettres III et VII. Puis, on verra en quoi l’exil d’Usbek, contraint à quitter la Perse, constitue une séparation et comment celle-ci finit par le rapprocher de ses eunuques. Enfin, on se penchera de façon plus approfondie sur la figure de l’eunuque, esclave dont on a amputé le sexe et qui semble ainsi incarner le mieux l’aliénation.

Educating future leaders in patient safety

Science.gov (United States)

Leotsakos, Agnès; Ardolino, Antonella; Cheung, Ronny; Zheng, Hao; Barraclough, Bruce; Walton, Merrilyn

2014-01-01

Education of health care professionals has given little attention to patient safety, resulting in limited understanding of the nature of risk in health care and the importance of strengthening systems. The World Health Organization developed the Patient Safety Curriculum Guide: Multiprofessional Edition to accelerate the incorporation of patient safety teaching into higher educational curricula. The World Health Organization Curriculum Guide uses a health system-focused, team-dependent approach, which impacts all health care professionals and students learning in an integrated way about how to operate within a culture of safety. The guide is pertinent in the context of global educational reforms and growing recognition of the need to introduce patient safety into health care professionals’ curricula. The guide helps to advance patient safety education worldwide in five ways. First, it addresses the variety of opportunities and contexts in which health care educators teach, and provides practical recommendations to learning. Second, it recommends shared learning by students of different professions, thus enhancing student capacity to work together effectively in multidisciplinary teams. Third, it provides guidance on a range of teaching methods and pedagogical activities to ensure that students understand that patient safety is a practical science teaching them to act in evidence-based ways to reduce patient risk. Fourth, it encourages supportive teaching and learning, emphasizing the need to establishing teaching environments in which students feel comfortable to learn and practice patient safety. Finally, it helps educators incorporate patient safety topics across all areas of clinical practice. PMID:25285012

Les présages expliqués

CERN Document Server

Belly

2015-01-01

Extrait : ""Les Romains et les Grecs avaient emprunté aux Chaldéens la plupart des arts divinatoires : Ce que disent les caractères de l'Écriture. Ce que disent les lignes du visage. Ce que disent les traits du visage. Ce que disent les cartes, etc.""

Safety Training: Ergonomie - Sensibilisation à l'ergonomie bureautique

CERN Multimedia

Laetitia Laddada

2005-01-01

Nous vous proposons une 1/2 journée de sensibilisation sur les risques engendrés par une mauvaise posture lors du travail sur écran (mal de dos, fatigue visuelle, douleurs des poignets...) et des bonnes pratiques pour y remédier. Les prochaines sessions auront lieu le 24 février 2005 (matin et après-midi). Les cours sont pris en charge par la Commission de Sécurité et animés par Pily Clemente et Marion Ribordy de « PM postures ». L'inscription via EDH est obligatoire. Pour plus d'information et inscription par EDH à ce cours, veuillez consulter les pages Formation et Développement (groupe sécurité) de HR, ou contacter l'organisateur. Les places seront attribuées dans l'ordre de réception des inscriptions. Organisateur : Ana-Paula Bernardes/SC-GS (71385) Ana-paula.bernardes@cern.ch FORMATION EN SECURITE SAFETY TRAINING Laetitia Laddada ...

Safety Training: Ergonomie - Sensibilisation à l'ergonomie bureautique

CERN Multimedia

Laetitia Laddada

2005-01-01

Nous vous proposons une 1/2 journée de sensibilisation sur les risques engendrés par une mauvaise posture lors du travail sur écran (mal de dos, fatigue visuelle, douleurs des poignets...) et des bonnes pratiques pour y remédier. Les prochaines sessions auront lieu le 24 février 2005 (matin et après-midi). Les cours sont pris en charge par la Commission de Sécurité et animés par Pily Clemente et Marion Ribordy de « PM postures ». L'inscription via EDH est obligatoire. Pour plus d'information et inscription par EDH à ce cours, veuillez consulter les pages Formation et Développement (groupe sécurité) de HR, ou contacter l'organisateur. Les places seront attribuées dans l'ordre de réception des inscriptions. Organisateur : Ana-Paula Bernardes/SC-GS (71385) Ana-paula.bernardes@cern.ch FORMATION EN SECURITE SAFETY TRAINING Laetitia Laddada 7...

Motorcycle Safety Education. A Curriculum Guide.

Science.gov (United States)

Ohio State Board of Education, Columbus.

This curriculum guide was produced to assist instructors of educational programs for novice motorcycle operators, automobile drivers, and all highway users. An introductory section discusses program implementation concerns, such as public relations, legal considerations, scheduling, staff, students, facilities, motorcycles, insurance, financial…

Controverses sur les sucres [Controversies about sugars

Directory of Open Access Journals (Sweden)

Malika BOUCHENAK

2016-12-01

Full Text Available La surconsommation de sucres ajoutés et leurs effets putatifs sur diverses pathologies cardiométaboliques continuent de susciter des controverses. Dans les années 1950, le taux élevé de maladies cardiovasculaires (MCV, chez les hommes Américains a conduit à des études sur le rôle des facteurs alimentaires, tels que le cholestérol, les phytostérols, l'excès de calories, les acides aminés, les graisses, les glucides, les vitamines et les minéraux, à influencer le risque de MCV. Dans les années 60, deux éminents physiologistes, plaidant pour des hypothèses causales divergentes de MCV, John Yudkin a identifié les sucres ajoutés comme agent primaire, tandis que Ancel Keys identifiait les graisses totales, les graisses saturées et le cholestérol alimentaire. Cependant, dans les années 80, peu de scientifiques croyaient que les sucres ajoutés jouaient un rôle important dans la maladie coronarienne, et les premiers conseils nutritionnels de 1980 (1980 Dietary Guidelines for americans étaient axés sur la réduction des graisses totales, des graisses saturées et du cholestérol alimentaire pour la prévention des MCV.

Comment diffuser les savoirs à travers les Alpes ?

Directory of Open Access Journals (Sweden)

Wolfgang Pfefferkorn

2009-03-01

Full Text Available CIPRA’s Future in the Alps Project aims at showcasing examples of successful implementation and successful projects in the Alps, and making available to others the extensive pool of experience and practical knowledge that lies in these projects. But how to transfer knowledge in an area of some 14 million inhabitants with several linguistic and cultural regions in which thousands of projects are carried out each year, that all kinds of players who work and life in completely different contexts are able to learn and benefit from one another? How do you go about something like that?Le projet « Avenir dans les Alpes » de la CIPRA (Commission Internationale pour la Protection des Alpes a pour objectif de présenter des exemples de réalisations et de projets réussis dans les Alpes, et de mettre à disposition du public l’ensemble de l’expérience et des connaissances pratiques acquises dans le cadre de ces projets. Cependant, comment transférer les savoirs dans une zone comptant quelque 14 millions d’habitants, composée de plusieurs régions linguistiques et culturelles dans lesquelles des milliers de projets sont menés à bien chaque année, et dont tous les acteurs, qui travaillent et vivent dans des contextes complètement différents, sont capables d’apprendre et de tirer profit les uns des autres ? Comment aborder ce genre de cas ?

Renforcer les partenariats entre les conseils subventionnaires de la ...

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

Les conseils subventionnaires de la recherche scientifique sont essentiels au financement et à la promotion de la recherche et de l'innovation. Une récente étude de délimitation de la portée financée par le CRDI a souligné le rôle important qu'ils jouent dans les réseaux scientifiques nationaux en Afrique subsaharienne.

LES VIBRIONS DANS LES PRODUITS DE LA PÊCHE

African Journals Online (AJOL)

PC_WINDOWS

Santé Publique (ENSP) à Rennes et le Centre National de Référence des vibrions et du Choléra (CNRVC) à l'Institut Pasteur ... l'Alimentation, en France, dans le but de normaliser les protocoles d'étude et de recherche de V. cholerae et ..... Vibrio présente dans l'environnement avec les méthodes de détection habituelles.

Efficacy, acceptability and safety of guided imagery/hypnosis in fibromyalgia - A systematic review and meta-analysis of randomized controlled trials.

Science.gov (United States)

Zech, N; Hansen, E; Bernardy, K; Häuser, W

2017-02-01

This systematic review aimed at evaluating the efficacy, acceptability and safety of guided imagery/hypnosis (GI/H) in fibromyalgia. Cochrane Library, MEDLINE, PsycINFO and SCOPUS were screened through February 2016. Randomized controlled trials (RCTs) comparing GI/H with controls were analysed. Primary outcomes were ≥50% pain relief, ≥20% improvement of health-related quality of life, psychological distress, disability, acceptability and safety at end of therapy and 3-month follow-up. Effects were summarized by a random effects model using risk differences (RD) or standardized mean differences (SMD) with 95% confidence intervals (CI).Seven RCTs with 387 subjects were included into a comparison of GI/H versus controls. There was a clinically relevant benefit of GI/H compared to controls on ≥50% pain relief [RD 0.18 (95% CI 0.02, 0.35)] and psychological distress [SMD -0.40 (95% CI -0.70, -0.11)] at the end of therapy. Acceptability at the end of treatment for GI/H was not significantly different to the control. Two RCTs with 95 subjects were included in the comparison of hypnosis combined with cognitive behavioural therapy (CBT) versus CBT alone. Combined therapy was superior to CBT alone in reducing psychological distress at the end of therapy [SMD -0.50 (95% CI -0.91, -0.09)]. There were no statistically significant differences between combined therapy and CBT alone in other primary outcomes at the end of treatment and follow-up. No study reported on safety. GI/H hold promise in a multicomponent management of fibromyalgia. We provide a systematic review with meta-analysis on guided imagery and hypnosis for fibromyalgia. Current analyses endorse the efficacy and tolerability of guided imagery/hypnosis and of the combination of hypnosis with cognitive-behavioural therapy in reducing key symptoms of fibromyalgia. © 2016 European Pain Federation - EFIC®.

LISA. A code for safety assessment in nuclear waste disposals program description and user guide

International Nuclear Information System (INIS)

Saltelli, A.; Bertozzi, G.; Stanners, D.A.

1984-01-01

The code LISA (Long term Isolation Safety Assessment), developed at the Joint Research Centre, Ispra is a useful tool in the analysis of the hazard due to the disposal of nuclear waste in geological formations. The risk linked to preestablished release scenarios is assessed by the code in terms of dose rate to a maximum exposed individual. The various submodels in the code simulate the system of barriers -both natural and man made- which are interposed between the contaminants and man. After a description of the code features a guide for the user is supplied and then a test case is presented

Les chercheurs ont constaté que le conflit touchait les femmes de ...

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

khaggart

Les chercheurs ont constaté que le conflit touchait les femmes de deux façons. Sur le plan juridique, elles ont des droits égaux à la terre, mais la société ne leur reconnaît guère ces droits. Les femmes déplacées qui ont perdu leur terre et leur mari (parce que celui-ci a été tué) souffrent d'une double injustice, car, en tant ...

Safety Training: Sensibilisation aux gestes et postures de travail

CERN Multimedia

Laetitia Laddada

2004-01-01

Nous vous proposons un nouveau cours de sécurité lié aux manutentions manuelles (durée 1 jour) : Sensibilisation aux gestes et postures de travail. Si vous êtes amené à manipuler régulièrement des charges lourdes ou volumineuses, cette formation peut vous aider à prévenir les lésions musculaires ou dorsales. A l'issue de cette formation, vous serez capable d'adopter et d'appliquer les principes de base de sécurité physique et d'économie d'efforts dans les manipulations d'objets. Les cours sont pris en charge par la Commission de Sécurité. L'inscription EDH est obligatoire. Pour plus d'information, veuillez consulter les pages Formation & Développement (Groupe Sécurité). Formation & Développement (Groupe Sécurité) FORMATION EN SECURITE SAFETY TRAINING Laetitia Laddada 73811 - 79236 sa...

Les paradoxes de la matière

CERN Document Server

2013-01-01

Si nous devons la multitude d’appareils numériques actuels à l’électronique, celle-ci atteint ses limites. Comment les dépasser ? En explorant les propriétés spectaculaires de la matière ! Et les candidats au remplacement de l’électronique sont nombreux : oxytronique, spintronique, plasmonique, magnonique, graphène... Nous réservant aussi bien d’autres surprises - tels les capes d’invisibilité, les plastiques conducteurs, les polymères autocicatrisants, les protections antisismiques, etc - les études sur la matière n’ont pas fini de nous étonner.

Les régions et les pays | CRDI - Centre de recherches pour le ...

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

Au CRDI, nous finançons la recherche qui permet aux pays en développement de créer le savoir et les solutions nécessaires pour apporter des changements durables. Nos quatre bureaux régionaux collaborent étroitement avec les collectivités qu'ils desservent en Asie, en Afrique, en Amérique latine et dans les Caraïbes, ...

Les plantes médicinales utilisées contre les dermatoses dans la ...

African Journals Online (AJOL)

SARAH

31 oct. 2013 ... Sterculiaceae avec chacune deux espèces. Toutes les autres familles sont représentées par une seule espèce. (Tableau 1). Tableau 1 : Liste des plantes utilisées contre les dermatoses chez les Bainounk de Djibonker, région de Ziguinchor. (Sénégal). Taxon. Famille. Indice de fidélité (FL%). Agave sp.

ÉTUDE DE CAS — Équateur (les pesticides) : L'intoxication par les ...

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

10 janv. 2011 ... Le projet s'est déroulé dans trois collectivités (La Libertad, Santa Martha de Cuba et San Pedro de Piartal) où les chercheurs ont entrepris un ambitieux programme combinant les données dela recherche et l'intervention active en vue d'améliorer la vie des familles agricoles. Dans un premier temps, les ...

Occupational safety meets radiation protection

International Nuclear Information System (INIS)

Severitt, S.; Oehm, J.; Sobetzko, T.; Kloth, M.

2012-01-01

The cooperation circle ''Synergies in operational Security'' is a joint working group of the Association of German Safety Engineers (VDSI) and the German-Swiss Professional Association for Radiation Protection (FS). The tasks of the KKSyS are arising from the written agreement of the two associations. This includes work on technical issues. In this regard, the KKSyS currently is dealing with the description of the interface Occupational Safety / Radiation Protection. ''Ignorance is no defense'' - the KKSyS creates a brochure with the working title ''Occupational Safety meets radiation protection - practical guides for assessing the hazards of ionizing radiation.'' The target groups are entrepreneurs and by them instructed persons to carry out the hazard assessment. Our aim is to create practical guides, simple to understand. The practical guides should assist those, who have to decide, whether an existing hazard potential through ionizing radiation requires special radiation protection measures or whether the usual measures of occupational safety are sufficient. (orig.)

Les violences conjugales à Dakar

Science.gov (United States)

Soumah, Mohamed Maniboliot; Issa, Abdoul Wahab; Ndiaye, Mor; Ndoye, El Hadj Oumar; Sow, Mamadou Lamine

2015-01-01

L'objectif était d’évaluer les aspects épidémiologiques des violences conjugales, identifier les facteurs de risques et les différents types de violences conjugales, évaluer les conséquences des violences conjugales sur la santé des victimes, afin d'améliorer la prise en charge des victimes et la prévention du phénomène. Il s'est agit d'une étude transversale effectuée de décembre 2012 à janvier 2013 à Dakar. Les données ont été recueillies, après consentement, sur fiche d'enquête anonyme soumise à toute personne volontaire vivant en couple et résidant à Dakar. L'analyse statistique a été effectuée avec le logiciel SPSS 13.0. Le nombre de personnes victimes de violences conjugales était de 60 soit 37,30% dont 31 femmes (51,70%) et 29 hommes (48,30%). Le sex-ratio était de 0,93. Parmi les victimes, 53 étaient scolarisées soit 88,30%. Le régime matrimonial était de type monogame dans 39 cas (65%) et polygame dans 21 cas (35%). La vie en couple durait depuis moins de 11 ans dans 60% des cas et durait de 11 ans à 20 ans au plus dans 26,6% des cas. L’étude des types de violences montrait la fréquence des agressions physiques. Les armes utilisées étaient surtout les armes naturelles. Les principaux facteurs de risque de violence conjugale sont les facteurs sociodémographiques, culturels et économiques comme le jeune âge, l'inégalité du genre, les jeunes couples, la précarité, le niveau d'instruction élevé. La prise en charge des victimes et la prévention du phénomène restent insuffisantes dans nos pays. PMID:26918077

Les chercheurs inquiets malgre les promesses de Claudie Haignere

CERN Multimedia

2003-01-01

"Le 9 avril, lors d'un colloque sur l'innovation, la ministre deleguee a la recherche et aux nouvelles technologies a annonce, "en plein accord, dit-elle, avec le premier ministre", que "les etablissements publics a caractere scientifique et technologique (EPST) ne connaitront en 2003 aucune nouvelle annulation de credits de paiement et d'autorisations de programme" et que "les reserves de precaution sont entierement levees" (1 page).

OGM Diffusion des OGM et impact pour les agriculteurs : quels sont les liens ?

Directory of Open Access Journals (Sweden)

Lemarie Stéphane

2001-05-01

Full Text Available Les OGM actuellement sur le marché présentent des innovations sur des fonctions de protection des plantes. Selon les problèmes de protection des plantes, les gains des agriculteurs liés à l’adoption des OGM sont très variables. Cette hétérogénéité pose d’importants problèmes méthodologiques pour pouvoir estimer correctement la distribution des gains pour l’ensemble des agriculteurs. Une synthèse de plusieurs études américaines est réalisée ici et met bien en évidence la diversité des méthodes utilisées, chacune d’elles présentant ses avantages et ses limites. Globalement, si la diffusion des OGM est un fait indéniable, les études ne permettent pas de tirer des conclusions aussi nettes quant à l’impact des OGM pour tous les agriculteurs qui adoptent ces produits, et cela en particulier pour le soja. Cette absence de conclusion s’explique en grande partie par la difficulté à mesurer certains facteurs qui influencent le comportement d’adoption, comme par exemple la simplification de la conduite des cultures. En contrepartie, il faut noter que les études présentées ici ne prennent pas en compte un certain nombre d’effets indirects qui peuvent faire diminuer les gains des agriculteurs.

Safety Training: Ergonomie - Sensibilisation à l'ergonomie bureautique - French version only

CERN Multimedia

Laetitia Laddada

2004-01-01

If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an 'application for training' form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt. Formation en SECURITE SAFETY Training Laetitia Laddada 73811 - 79236 safety.training@cern.ch Nous vous proposons une 1/2 journée de sensibilisation sur les risques engendrés par une mauvaise posture lors du travail sur écran (mal de dos, fatigue visuelle, douleurs des poignets...) et des bonnes pratiques pour y remédier. Les prochaines sessions auront lieu le 8 juillet 2004. Les cours sont pris en charge par la Commission de Sécurité et animés par Clemente Pilly et Ribordy Marion de « PM postures &ra...

Demande de sécurité des véhicules et normes automobiles depuis les années 1960

Directory of Open Access Journals (Sweden)

Marine Moguen-Toursel

2008-12-01

Full Text Available Ce papier met l’accent sur l’émergence de la sécurité routière au plan communautaire comme un enjeu important de société, en réponse au problème criant du nombre des morts sur la route (qui connaît un pic au début des années 1970. Ce moment de prise de conscience correspond à une irruption des pouvoirs publics sur ces questions tant au plan national qu’au plan communautaire. Toutefois, les traductions en termes de réglementations sont lentes à apparaître. La Commission européenne doit inventer de nouvelles procédures pour obtenir des avancées en la matière. Depuis que des gains importants ont été chiffrés en termes de pénétration des innovations de sécurité des véhicules sur les marchés automobiles européens (impliquant une amélioration de compétitivité pour cette industrie, les pressions pour adopter une réglementation uniforme (notamment entre les standards communautaires et internationaux se font plus fortes et les investissements dans la R&D se font plus lourds (même s’ils restent loin des niveaux américains. L’obstacle réside surtout à présent dans l’absence de demande de la part des consommateurs européens pour ces technologies et la méconnaissance par les utilisateurs des outils de sécurité présents à bord des véhicules.Au plan de la gouvernance, ces thématiques sont prises en charge par un nombre croissant d’acteurs (il est intéressant de noter que les premiers intervenants sur ces dossiers sont les constructeurs, puis les pouvoirs publics et enfin les associations de consommateurs. Les travaux évoluent vers une approche intégrée faisant intervenir les différents acteurs bien en amont de la décision finale au sein de forums de discussion.This paper focuses on the emergence of road safety at the Community level as an important societal stake, answering the very urgent problem of number of deaths on the roads (which was particularly high at the beginning of the 1970s. This

Putting Safety in the Frame

Directory of Open Access Journals (Sweden)

Valerie Jean O’Keeffe

2015-06-01

Full Text Available Current patient safety policy focuses nursing on patient care goals, often overriding nurses’ safety. Without understanding how nurses construct work health and safety (WHS, patient and nurse safety cannot be reconciled. Using ethnography, we examine social contexts of safety, studying 72 nurses across five Australian hospitals making decisions during patient encounters. In enacting safe practice, nurses used “frames” built from their contextual experiences to guide their behavior. Frames are produced by nurses, and they structure how nurses make sense of their work. Using thematic analysis, we identify four frames that inform nurses’ decisions about WHS: (a communicating builds knowledge, (b experiencing situations guides decisions, (c adapting procedures streamlines work, and (d team working promotes safe working. Nurses’ frames question current policy and practice by challenging how nurses’ safety is positioned relative to patient safety. Recognizing these frames can assist the design and implementation of effective WHS management.

Punção Aspirativa por Agulha Fina Orientada por Ultra-Sonografia em Lesões Não-palpáveis Fine Needle Aspiration Cytology Guided by Ultrasound in Nonpalpable Lesions

Directory of Open Access Journals (Sweden)

Cláudio Kemp

2001-06-01

Full Text Available Objetivo: correlacionar os achados citológicos obtidos por punção com agulha fina dirigida pela ultra-sonografia de lesões não-palpáveis da mama, císticas ou sólidas, os aspectos ultra-sonográficos e os respectivos resultados histopatológicos das lesões que foram submetidas a cirurgia. Métodos: foram analisadas 617 lesões não-palpáveis visualizadas ao ultra-som. Realizou-se a punção aspirativa por agulha fina (PAAF orientada pela ultra-sonografia, com análise citológica do material, diferenciando-as em cistos ou nódulos sólidos. Estes tiveram seu resultado citológico confrontado com o resultado histopatológico, nos casos em que foi realizada a biópsia cirúrgica. Resultados: das 617 lesões não-palpáveis, 471 eram cistos, sendo 451 cistos simples que apresentaram citologia negativa em todos os casos e 20 casos foram considerados cistos complexos. Destes, 3 (15% tiveram resultado citológico positivo ou suspeito e em 2 casos confirmou-se malignidade. Dos 105 nódulos sólidos, 63 apresentaram citologia negativa, sendo 59 concordantes com a biópsia e houve 4 casos (0,3% de resultado falso-negativo pela citologia. Todos, porém, apresentavam discordância entre imagem e citologia. Em 14 nódulos sólidos (13%, a citologia foi suspeita e, destes, 5 foram diagnosticados como carcinoma. Em outros 14 (13%, o material foi insatisfatório e 1 era carcinoma. Em 51 casos, o tríplice diagnóstico foi concordante e optou-se por seguimento clínico. Conclusão: a análise citológica do material dos cistos mamários simples é desnecessária, porém quando são complexos, a citologia é imperativa. Nas lesões sólidas não-palpáveis, é fundamental a correlação da citologia com o aspecto ultra-sonográfico e mamográfico; caso sejam discordantes, deve-se sempre prosseguir a investigação da lesão.Purpose: to determine the relationship between fine needle aspiration cytology guided by ultrasound of nonpalpable breast lesions

Les coopératives, sources d'espoir pour les Marocaines | CRDI ...

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

exploiter une ressource forestière fort précieuse qui est menacée, l'arganier, ont permis de hausser considérablement les revenus des femmes berbères. Regroupées en petites coopératives, les femmes produisent de l'huile ...

Respect par les Canadiens de 10 à 17 ans des Directives canadiennes en matière de mouvement sur 24 heures pour les enfants et les jeunes

Directory of Open Access Journals (Sweden)

Ian Janssen

2017-01-01

Full Text Available Introduction : Le document Directives canadiennes en matière de mouvement sur 24 heures pour les enfants et les jeunes publié en 2016 contient des recommandations quant à l’activité physique quotidienne d’intensité moyenne à élevée, au temps de loisir passé devant un écran et au sommeil chez les jeunes de 5 à 17 ans. Cette étude a pour objectif d’estimer le pourcentage de Canadiens de 10 à 17 ans qui respectent ces recommandations. Méthodologie : Nous avons analysé un échantillon national représentatif de 22 115 jeunes. Les données sur le comportement actif ont été autodéclarées. Le respect des recommandations des Directives repose sur les éléments suivants : accumulation d’au moins 60 minutes par jour d’activité physique d’intensité moyenne à élevée, pas plus de 2 heures par jour de temps de loisir passé devant un écran et de 9 à 11 heures de sommeil continu par nuit pour les jeunes de 10 à 13 ans ou de 8 à 10 heures de sommeil continu par nuit pour les jeunes de 14 à 17 ans. Résultats : Seulement 3 % des jeunes de l’échantillon respectaient les trois recommandations clés. Vingt-cinq pour cent respectaient deux recommandations, 51 % en respectaient une et 21 % n’en respectaient aucune. La recommandation en matière de sommeil était la plus respectée par les enfants et les jeunes (66 %, suivie de celle en matière d’activité physique d’intensité moyenne à élevée (35 % et de celle relative au temps passé devant un écran (8 %. Conclusion : Une faible proportion (moins de 3 % de Canadiens de 10 à 17 ans respectent les trois principales recommandations des Directives canadiennes en matière de mouvement sur 24 heures pour les enfants et les jeunes.

Les infestations par les poux de tête : une mise à jour clinique.

Science.gov (United States)

Cummings, Carl; Finlay, Jane C; MacDonald, Noni E

2018-02-01

Les infestations par les poux de tête ( Pediculus humanus capitis ) ne constituent ni un risque sanitaire primaire ni un vecteur de maladie, mais représentent plutôt un problème de société au coût impor- tant. Pour diagnostiquer une infestation, il faut déceler un pou vivant. Même si les pyréthines et la perméthrine demeurent les traitements de première intention au Canada, la solution de myristate d'isopropyle et de ST-cyclométhicone et la diméticone peuvent être envisagées en deuxième intention après un échec thérapeutique démontré.

Quand le crédit à la consommation classe les gens et les choses

DEFF Research Database (Denmark)

Ossandón, José

2012-01-01

Le développement du crédit à la consommation est l’une des principales manifestations de la financiarisation de l’économie. Les éléments institutionnels et techniques qui lui ont donné forme tels que les dispositifs d’attribution de score aux consommateurs, de détermination des taux ou encore les...

Les pensions dans les pays de l'OCDE 2009 panorama des systèmes de retraite

CERN Document Server

Organisation for Economic Cooperation and Development. Paris

2009-01-01

Les politiques menées en matière de pensions et de retraite ont connu des évolutions considérables au cours des dernières années, les pouvoirs publics s’efforçant de concilier deux objectifs : assurer des revenus suffisants aux retraités et garantir la viabilité financière à long terme des systèmes de retraite face au vieillissement de la population. Panorama des Pensions 2009 propose un cadre de référence cohérent permettant de comparer les politiques adoptées dans ce domaine par les différents pays de l’OCDE, ainsi qu’un ensemble de données fiables. Cette troisième édition renferme des informations actualisées sur les principales caractéristiques des pensions versées au sein des pays de l’OCDE et contient des projections relatives aux revenus que percevront demain les salariés d’aujourd’hui. Elle offre également une gamme élargie d’indicateurs, parmi lesquels figurent des données chiffrées concernant les actifs, les performances des investissements, l’ampleur des ...

Les Africaines Et Les Tic

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

Enquête sur les technologies, la question de genre et autonomisation ...... Polachek, S. (1981) «Occupational self-selection: a human capital approach to sex ...... in the Computer Science major », Communications of the ACM, 44(5) : 108–14.

SANTÉ PUBLIQUE Les troubles de santé font fi des frontières – les ...

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

SANTÉ PUBLIQUE Les troubles de santé font fi des frontières – les connaissances et les solutions devraient elles ... Dangers du tabac et des narguilés pour la santé ... ÉTUDE DE CAS : Nouvelles armes dans la guerre contre le paludisme.

Safer electronic health records safety assurance factors for EHR resilience

CERN Document Server

Sittig, Dean F

2015-01-01

This important volume provide a one-stop resource on the SAFER Guides along with the guides themselves and information on their use, development, and evaluation. The Safety Assurance Factors for EHR Resilience (SAFER) guides, developed by the editors of this book, identify recommended practices to optimize the safety and safe use of electronic health records (EHRs). These guides are designed to help organizations self-assess the safety and effectiveness of their EHR implementations, identify specific areas of vulnerability, and change their cultures and practices to mitigate risks.This book pr