IAEA Safety Standards Series – serie
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74 produkter
74 produkter
Operational Limits and Conditions and Operating Procedures for Research Reactors
Häftad, Engelska, 2023
540 kr
Skickas inom 5-8 vardagar
This Safety Guide is a revision of IAEA Safety Standards Series No. NS-G-4.4, which it supersedes. The revised version provides specific recommendations on developing, formulating and presenting the operational limits and conditions as well as the operating procedures for research reactors, to meet the relevant requirements of IAEA Safety Standards Series No. SSR-3, Safety of Research Reactors. The recommendations in this publication are intended for use by operating organizations of research reactors, regulatory bodies and other relevant organizations involved in a research reactor project.
Human Factors Engineering in the Design of Nuclear Power Plants
Specific Safety Guide
Häftad, Engelska, 2019
556 kr
Skickas inom 11-20 vardagar
This publication provides recommendations and guidance for meeting Requirement 32 of IAEA Safety Standards Series No. SSR-2/1 (Rev. 1), Safety of Nuclear Power Plants: Design, for optimal operator performance involving systematic consideration of human factors, including the human machine interface (HMI). The Safety Guide provides a structured approach and guidance on application of human factors engineering (HFE) in the design of the HMI, which is the basis for human physical and cognitive processes in nuclear power plants. It applies to application of HFE in the design, operation and maintenance of the HMI for new plants, as well as for modifications of the HMI of existing plants.
Protection Against Internal and External Hazards in the Operation of Nuclear Power Plants
Häftad, Engelska, 2022
580 kr
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This Safety Guide provides specific recommendations on protection against internal and external hazards in the operation of nuclear power plants. It provides new or updatedrecommendations derived from enhanced understanding of operational aspects of hazards and combinations of hazards. Operating experience gained from incidents and accidents in nuclear power plants around the world has demonstrated that fire can be an important risk contributor in many Member States. However, there are other internal and external hazards that have also to be considered in the design and operation of nuclear power plants. This Safety Guide supersedes and expands the scope of lAEA Safety Standards Series No. NS- G-2. 1, Fire Safety in the Operation of Nuclear Power Plants, to include recommendations on these other hazards.
766 kr
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This Safety Guide provides recommendations on safety in the siting, design, construction, commissioning, operation and preparation for the decommissioning of nuclear fuel reprocessing facilities to meet the relevant requirements established in the IAEA Safety Standards Series No. SSR-4, Safety of Nuclear Fuel Cycle Facilities. It provides specific recommendations on the safety of nuclear fuel reprocessing facilities that use the PUREX process to reprocess fuels containing uranium and plutonium. It does not specifically address the reprocessing of thorium from fast breeder reactors or other advanced reactor systems, or the partitioning of radionuclides other than uranium and plutonium. However, the similarity between aqueous processes allows for the application of most of the recommendations provided in this Safety Guide, with suitable adjustments to facilities reprocessing other types of nuclear fuel. This publication is intended for operating organizations and designers of nuclear fuel reprocessing facilities and relevant technical support organizations and regulatory bodies.
753 kr
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This Safety Guide provides recommendations on safety in the siting, design, construction, commissioning, operation and preparation for the decommissioning of nuclear fuel research and development facilities to meet the relevant requirements established in IAEA Safety Standards Series No. SSR-4, Safety of Nuclear Fuel Cycle Facilities. It applies to all types of nuclear fuel cycle research and development facility, including facilities involving small scale experiments, analyses and fundamental research studies on the chemical, physical, mechanical and radiological properties of specific materials such as prototype nuclear fuels (before and after reactor irradiation) and investigations of nuclear materials and wastes arising from new processes, and facilities involving research and development on processes and equipment envisaged for use on an industrial scale (e.g. pilot facilities for waste treatment). This publication is intended for operating organizations and designers of nuclear fuel cycle research and development facilities and relevant technical support organizations and regulatory bodies.
Instrumentation and Control Systems and Software Important to Safety for Research Reactors
specific safety guide
Häftad, Engelska, 2015
500 kr
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This Safety Guide provides recommendations and guidance on instrumentation and control systems and software important to safety for research reactors, including instrumentation and control system architecture and associated components, from sensors to actuators, operator interfaces and auxiliary equipment. It also provides recommendations on computer based systems and software, including software requirements and design, verification and validation, integration, and operation. This publication also addresses safety classification, design, implementation, qualification and operation of instrumentation as well as control systems. The recommendations and guidance apply to both the design and configuration management of instrumentation and control systems for new research reactors and the modernization of the instrumentation and control systems to existing research reactor facilities. In addition, this Safety Guide provides recommendations and guidance on human factors engineering and human-machine interfaces, and for computer based systems and software for use in instrumentation and control systems important to safety.
Radiation Protection and Radioactive Waste Management in the Design and Operation of Research Reactors
Häftad, Engelska, 2023
633 kr
Skickas inom 5-8 vardagar
This Safety Guide provides recommendations on radiation protection and radioactive waste management in the design and operation of research reactors, to meet the relevant requirements of IAEA Safety Standards Series No. SSR-3, Safety of Research Reactors. It identifies important components that should be considered at the design stage with regard to facilitating radiation protection and radioactive waste management. It also recommends good practices in implementing operational radiation protection and radioactive waste management programmes, and in their optimization. This Safety Guide is a revision of IAEA Safety Standards Series No. NS-G-4.6, which it supersedes.
487 kr
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This Safety Guide provides practical guidance and recommendations on ageing management for research reactors, to meet the relevant requirements of IAEA Safety Standards Series No. SSR-3, Safety of Research Reactors. It is intended for use by operating organizations in establishing, implementing and improving ageing management programmes for research reactors, and by regulatory bodies in verifying that ageing of research reactors is being effectively managed. The Safety Guide focuses on managing the physical ageing of systems, structures and components important to safety, and also provides guidance on safety aspects of managing obsolescence. This Safety Guide is a revision of IAEA Safety Standards Series No. SSG-10, which it supersedes.
Instrumentation and Control Systems and Software Important to Safety for Research Reactors
Häftad, Engelska, 2023
553 kr
Skickas inom 5-8 vardagar
This publication provides specific recommendations on research reactor instrumentation and control systems and software important to safety, including instrumentation and control system architecture and associated components, from sensors to actuators, operator interfaces and auxiliary equipment, to meet the relevant requirements of IAEA Safety Standards Series No. SSR-3, Safety of Research Reactors. The recommendations and guidance apply to both the design and configuration management of instrumentation and control systems for new research reactors and the modernization of the instrumentation and control systems at existing research reactor facilities. In addition, this Safety Guide provides recommendations and guidance on human factors engineering and human-machine interfaces, and for computer based systems and software for use in instrumentation and control systems important to safety. This Safety Guide is a revision of IAEA Safety Standards Series No. SSG-37, which it supersedes.
570 kr
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This Safety Guide provides recommendations on meeting the requirements established in IAEA Safety Standards Series No. SSR-6 (Rev. 1), Regulations for the Safe Transport of Radioactive Material, 2018 Edition, for a radiation protection programme for the transport of radioactive material. The objectives of a radiation protection programme for the transport of radioactive material are to provide for adequate consideration of radiation protection measures in transport; to ensure that the system of radiological protection is adequately applied; to enhance a safety culture in the transport of radioactive material; and to provide practical measures to meet these objectives. The recommendations provided in this Safety Guide are applicable to the transport of radioactive material by all modes on land, water, or in the air, including transport that is incidental to the use of the radioactive material. The intended audience for this Safety Guide includes competent authorities, consignors, carriers, consignees, and operators of ports (e.g. harbours, seaports and airports). It will also be of interest to the employees of public authorities (customs authorities, harbour authorities, port authorities) concerning activities associated with the transport of radioactive material that involve radiation exposure.
Decommissioning of Nuclear Power Plants, Research Reactors and Other Nuclear Fuel Cycle Facilities
Specific Safety Guide
Häftad, Engelska, 2018
487 kr
Skickas inom 5-8 vardagar
Decommissioning is the last step in the lifetime management of an authorized facility and it must be considered during the design, construction, commissioning and operation of such facilities. This publication provides guidance on how to comply with requirements for the safe decommissioning of nuclear power plants, research reactors, and other nuclear fuel cycle facilities. It addresses all the aspects of decommissioning that are required to ensure safety including: roles and responsibilities, strategy and planning for decommissioning, conduct of decommissioning actions and completion of decommissioning. It is intended for use by those working in policy and strategy development, planning, implementation and regulatory control of decommissioning.
Ageing Management and Development of a Programme for Long Term Operation of Nuclear Power Plants
Specific Safety Guide
Häftad, Engelska, 2018
527 kr
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This Safety Guide supplements and provides recommendations on meeting the requirements related to ageing management and long term operation that are established in IAEA Safety Standards Series No. SSR-2/1 (Rev.1), Safety of Nuclear Power Plants: Design, and IAEA Safety Standards Series No. SSR-2/2 (Rev.1), Safety of Nuclear Power Plants: Commissioning and Operation. It provides guidance for operating organizations on implementing and improving ageing management and, obsolescence management and on developing a programme for safe long term operation for nuclear power plants. It may also be used by the regulatory body in preparing regulatory requirements, codes and standards, and in verifying effective ageing management, obsolescence management and preparation for safe long term operation of nuclear power plants.
367 kr
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This Safety Requirements publication establishes requirements that support Principle 3 of the Fundamental Safety Principles in relation to establishing, sustaining and continuously improving leadership and management for safety and an integrated management system. It emphasizes that leadership for safety, management for safety, an effective management system and a systemic approach (i.e. an approach in which interactions between technical, human and organizational factors are duly considered) are all essential to the specification and application of adequate safety measures and to the fostering of a strong safety culture. Leadership and an effective management system will integrate safety, health, environmental, security, quality, human-and-organizational factors, societal and economic elements. The management system will ensure the fostering of a strong safety culture, regular assessment of performance and the application of lessons from experience. The publication is intended for use by regulatory bodies, operating organizations and other organizations concerned with facilities and activities that give rise to radiation risks.
Preparedness and Response for a Nuclear or Radiological Emergency
general safety requirements
Häftad, Engelska, 2015
540 kr
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This publication, jointly sponsored by the FAO, IAEA, ICAO, ILO, IMO, INTERPOL, OECD/NEA, PAHO, CTBTO, UNEP, OCHA, WHO and WMO, is the new edition establishing the requirements for preparedness and response for a nuclear or radiological emergency which takes into account the latest experience and developments in the area. It supersedes the previous edition of the Safety Requirements for emergency preparedness and response, Safety Standards Series No. GS-R-2, which was published in 2002. This publication establishes the requirements for ensuring an adequate level of preparedness and response for a nuclear or radiological emergency, irrespective of its cause. These Safety Requirements are intended to be used by governments, emergency response organizations, other authorities at the local, regional and national levels, operating organizations and the regulatory body as well as by relevant international organizations at the international level.
Design of the Reactor Coolant System and Associated Systems for Nuclear Power Plants
Häftad, Engelska, 2020
580 kr
Skickas inom 5-8 vardagar
This Safety Guide provides recommendations on how to meet the requirements established in IAEA Safety Standards Series No. SSR-2/1(Rev. 1) in relation to the reactor coolant system and associated systems for nuclear power plants. It is a revision of IAEA Safety Standards Series No. NS-G-1.9 which it supersedes. The publication takes into account developments, experience and practices in the design of nuclear power plants throughout their lifetime. It references and considers other IAEA safety standards that are relevant and related to the design of the reactor coolant system and associated systems for nuclear power plants. Recommendations to achieve the required reliability of the capabilities designed to transfer residual heat to the ultimate heat sink in the different plant states are also included. As those systems are dependent on specific reactor technologies, more appropriate recommendations have been developed for pressurized light water reactors, boiling water reactors and pressurized heavy water reactors respectively.
513 kr
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Radioisotopes are used worldwide in a range of medical, industrial, research and academic applications. A large proportion of these radioisotopes are produced in particle accelerators and the number of institutions that operate linear accelerators or cyclotrons and manufacture and distribute radiopharmaceuticals, for example, is significant and increasing. The production of radioisotopes using particle accelerators poses significant radiation hazards to workers, members of the public, and the environment when accelerators are operated without adequate radiation safety measures. This Safety Guide provides practical guidance for implementing radiation protection and safety measures in such facilities involved in the production and use of radioisotopes.
620 kr
Skickas inom 5-8 vardagar
There are several hundred thousand nuclear gauges incorporating a radioactive source or a radiation generator in use all over the world. They have been used in a wide range of industries to improve the quality of products, optimize processes, and save energy and materials. The economic benefits have been amply demonstrated, and there is clear evidence that nuclear gauge technology can be used safely and will continue to play an important role. Although generic guidance for source handling is available, there have been no targeted recommendations for radiation safety in the use of nuclear gauges. To fill this gap the current publication provides practical guidance for implementing the safety requirements specified in IAEA Safety Standards Series No. GSR Part 3, Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards, related to the use of nuclear gauges
633 kr
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This Safety Guide provides recommendations on the structure and content of the safety analysis report to be submitted by the operating organization to the regulatory body for authorization of the siting, construction, commissioning, operation and decommissioning of a nuclear power plant. It is intended to facilitate both the development of the safety analysis report by the operating organization and the checking of its completeness and adequacy by the regulatory body. The publication is a revision of IAEA Safety Standards Series No. GS?G?4.1, Format and Content of the Safety Analysis Report for Nuclear Power Plants, which it supersedes. The revision reflects feedback experience from the Fukushima Daiichi accident and the subsequent stress tests performed. It also describes good practices and experience from the use of safety analysis reports for newly built nuclear power plants in different States and informs on recent progress made in approaches to safety assessment.
Regulations for the Safe Transport of Radioactive Material
2018 Edition: Specific Safety Requirements
Häftad, Engelska, 2018
593 kr
Skickas inom 5-8 vardagar
The transport of radioactive material is an essential activity worldwide. Both safety and security during transport are matters of national and international importance. This publication is the latest edition of the IAEA Safety Requirements for the safe transport of radioactive material. It is supported by six IAEA Safety Guides which provide explanation and guidance for the SSR-6 requirements to facilitate harmonized implementation. The SSR-6 Regulations apply to the transport of radioactive material by all modes on land, water, or in the air, including transport that is incidental to the use of the radioactive material.Transport comprises all operations and conditions associated with, and involved in, the movement of radioactive material; these include the design, manufacture, maintenance and repair of packaging, and the preparation, consigning, loading, carriage including in-transit storage, unloading and receipt at the final destination of loads of radioactive material and packages. These requirements form an integral part of regulations worldwide, therefore SSR-6 and its associated guidance documents are a requisite source of guidance information for governments, regulators, and all individuals involved in the aforementioned activities of transport of radioactive material.These requirements are adopted into the UN Model Regulations which are subsequently adopted by the IMDG Code by the International Maritime Organisation for shipment by sea and by the International Civil Aviation Organization Technical Instructions for shipment by air. Both the IMDG Code and the ICAO Technical Instructions are globally implemented and mandatory. Land transport is the responsibility of the national government of each Member State, and the SSR-6 requirements are adopted for national transport safety regulations for shipments on land.
380 kr
Skickas inom 5-8 vardagar
This Safety Guide provides recommendations on how to meet the requirements of IAEA Safety Standards Series No. SSR?2/1 (Rev. 1), Safety of Nuclear Power Plants: Design, in relation to fuel handling and storage systems. The publication addresses the design aspects of handling and storage systems for fuel that remain part of the operational activities of a nuclear reactor. It covers the following stages of fuel handling and storage in a nuclear power plant: receipt, storage and inspection of fresh fuel before use and transfer of fresh fuel into the reactor; removal of irradiated fuel from the reactor and transfer of the irradiated fuel to the spent fuel pool; and reinsertion of irradiated fuel from the spent fuel pool into the reactor. Recommendations are also provided on the storage, inspection and repair of irradiated or spent fuel in the spent fuel pool, and the preparation for the removal of this fuel from the spent fuel pool and on the handling of fuel casks in the spent fuel pool and on their transfer.
367 kr
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This Safety Requirements publication takes into account and incorporates developments relating to site evaluation for nuclear installations since the publication of IAEA Safety Standards Series No. NS-R-3 in 2003. It applies IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles. Requirements for site evaluation are intended to contribute to the adequate protection of site personnel and the public and protection of the environment from harmful effects of ionizing radiation arising from nuclear installations. It is recognized that there are steady advances in technology and scientific knowledge, in nuclear safety and in what is considered adequate protection. Safety requirements evolve with these advances and this publication reflects the present consensus among States.
Establishing the Safety Infrastructure for a Nuclear Power Programme
Specific Safety Guide
Häftad, Engelska, 2020
607 kr
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This Safety Guide provides recommendations on the establishment of a framework for safety in accordance with the IAEA safety standards for States deciding on and preparing to embark on a nuclear power programme. In this regard, it proposes 197 safety related actions to be taken in the first three phases of the development of the nuclear power programme, to achieve the foundation for a high level of safety throughout the entire lifetime of the nuclear power plant (NPP). This includes safety in the construction, commissioning, and operation of the NPP and the associated management of radioactive waste and spent fuel, and safety in decommissioning. Thus, it contributes to the building of leadership and management for safety and of an effective safety culture and serves as guidance for self-assessment by all organizations involved in the development of a safety infrastructure.
Predisposal Management of Radioactive Waste from the Use of Radioactive Material in Medicine, Industry, Agriculture, Research and Education
Häftad, Engelska, 2019
487 kr
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This Safety Guide is applicable to the predisposal management of radioactive waste derived from the use of radioactive materials in medicine, industry, agriculture, research and education, including disused sealed radioactive sources. It focuses on waste generated at facilities such as hospitals and research centres, where radioactive waste is not usually generated in bulk quantities. It covers the managerial, administrative and technical issues associated with the safe management of radioactive waste, from its generation to its acceptance at a disposal facility or its release from regulatory control.
313 kr
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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.
840 kr
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This publication is the latest edition of IAEA Safety Standards Series No. SSR-6, Regulations for the Safe Transport of Radioactive Material. It is supported by seven IAEA Safety Guides which provide recommendations for meeting the requirements in SSR-6 to facilitate worldwide implementation. The regulations apply to the transport of radioactive material by all modes on land, water or in the air. Transport comprises the design, manufacture, maintenance and repair of packaging, and the preparation, consigning, loading, carriage including in-transit storage, shipment after storage, unloading and receipt at the final destination of loads of radioactive material and packages. These requirements form an integral part of regulations worldwide; therefore, SSR-6 and its associated Safety Guides are aimed at governments, competent authorities, and all organizations and individuals involved in the transport of radioactive material. These requirements are transcribed into the UN Model Regulations, which are subsequently transcribed into the IMDG Code by the International Maritime Organisation for shipment by sea, and into the Technical Instructions for the Safe Transport of Dangerous Goods by Air by the International Civil Aviation Organization. Both the IMDG Code and the ICAO Technical Instructions are globally implemented and mandatory. Land transport is the responsibility of the national government of each Member State, hence the SSR-6 requirements are adopted for national transport safety regulations for shipments on land.
540 kr
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Internal hazards have to be considered in the design of items important to safety in a nuclear powerplant. The objective is to provide appropriate features to prevent internal hazards and mitigate their effects toensure that safety is not compromised. This Safety Guide provides recommendations to regulatory bodies, nuclearpower plant designers and licensees on hazard assessment (including for combinations of hazards) and designconcepts for protection against internal hazards in nuclear power plants, in order to meet the requirementsestablished in IAEA Safety Standards Series No. SSR 2/1 (Rev. 1), Safety of Nuclear Power Plants: Design. Thefollowing internal hazards are reviewed in this Safety Guide: fires, explosions, missiles, pipe breaks, flooding,collapse of structures and falling objects with a focus on heavy load drop, electromagnetic interference and releaseof hazardous substances originating from within the site boundary.
- Nyhet
727 kr
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This Safety Guide provides recommendations on geotechnical engineering aspects that are important to the safety of nuclear installations, such as site investigation planning, evaluation of geotechnical hazards, considerations for design and analyses, monitoring of geotechnical parameters, and the application of a graded approach to geotechnical evaluations for nuclear installations other than large nuclear power plants, excluding nuclear waste disposal facilities. This publication is intended for use by operating organizations, licensees and regulatory bodies involved in the licensing of nuclear installations as well as designers and technical support organizations of such installations.
380 kr
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This Safety Guide provides recommendations on how to meet the applicable safety requirements in relation to the design aspects of new nuclear installations subjected to seismic hazard. These recommendations focus on the consistent application of methods and procedures, in accordance with best practice, for seismic analysis, design, testing and qualification of structures, systems and components. New recommendations include applications of seismic isolation systems, the seismic margin to be achieved by the design and application of the graded approach. This Safety Guide is intended for use by organizations involved in the seismic design of nuclear installations, in analysis, verification and review, and in the provision of technical support, as well as by regulatory bodies.
553 kr
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The objectives of nuclear criticality safety are to prevent a self-sustained nuclear chain reaction. 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 recommendations address how to ensure subcriticality in systems involving fissile materials during normal operation and during credible abnormal conditions, from initial design through commissioning, operation and decommissioning. This publication also provides recommendations on identification of credible abnormal conditions; performance of criticality safety assessments; verification, benchmarking and validation of calculation methods; safety measures to ensure subcriticality; and management of criticality safety. The guidance and recommendations are applicable to both regulatory bodies and operating organizations.
420 kr
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Written for use by regulatory bodies and the operating organizations of nuclear power plants, this Safety Guide addresses the commissioning, operation and preparation for decommissioning stages for a nuclear power plant. The role of the operating organization in the siting, design, manufacturing and construction of a nuclear power plant is outside the scope. In most States, the operating organization is the legal entity responsible for safety, financial and commercial obligations, as well as other obligations that are connected with the operation of a nuclear power plant. This Safety Guide is solely concerned with those responsibilities and obligations that are necessary to ensure the safe operation of the nuclear power plant(s) under the control of the operating organization.