The IAEA Safety Glossary defines and explains technical terms used in the IAEA Safety Standards and other safety related IAEA publications, and provides information on their usage. The 2018 Edition of the IAEA Safety Glossary is a new edition of the IAEA Safety Glossary, originally issued in 2007. It has been revised and updated to take into account new terminology and usage in safety standards issued between 2007 and 2018. The revisions and updates reflect developments in the technical areas of application of the safety standards and changes in regulatory approaches in Member States.

In the context of the safe management of disused sealed radioactive sources, an important and emerging issue of immediate concern is the management of depleted uranium (DU) contained in radiation shielding materials, as potential radioactive waste. This publication presents relevant information on technical issues and factors, as well as specific Member State experiences leading to the identification of potential options for the management of DU shields. Various options for safe, secure and cost-effective solutions have been explored, ranging from returning to manufacturer, including reuse, recycling, storage and disposal in licensed facilities.

Nuclear energy and renewables are the two principal options for low carbon energy generation. However, synergies among these resources have yet to be fully exploited, and the advantages of directly integrating these generation options are being explored. Nuclear-renewable hybrid energy systems consider opportunities to couple these energy generation sources to leverage the benefits of each technology to provide reliable, sustainable electricity to the grid and to provide low carbon energy to other energy use sectors. This publication describes the potential use of nuclear and renewable generation in coordinated, and in some cases tightly coupled, configurations to support various applications beyond electricity production, including desalination, hydrogen production and district heating. Where available, case studies are presented to describe relevant market conditions and trends, and considerations for implementation are outlined, including gaps that require additional technology and regulatory developments.

Hazards associated with human induced external events (HIEEs) need to be considered in the evaluation of sites for nuclear installations, in the design of new nuclear installations and in the operation of existing nuclear installations. This Safety Guide provides recommendations on the evaluation of these hazards in order to meet the requirements set out in IAEA Safety Standards Series No. SSR-1, Site Evaluation for Nuclear Installations. It provides a process for identification of source of HIEEs, screening of hazards using distance and probability, and detailed evaluation to establish hazard and load characterization parameters. This publication is intended for use by organizations involved in the identification, screening, analysis, evaluation and review of hazards associated with HIEEs, and the provision of technical support, as well as regulatory bodies.

Wave, tidal and offshore wind technologies have long held the promise of seemingly limitless energy supplies. In practice, while offshore wind is growing relatively rapidly, all three sectors have lagged behind expectations. This book, from the International Energy Authority Renewable Energy Technology Deployment implementing agreement (IEA-RETD), examines the reasons for this and suggests how barriers to deployment might be overcome. Beginning with an assessment of the marine energy resource, it provides a detailed introduction to the main technologies currently being employed to harness wind, tidal and offshore wind power. It then examines the types of policies which are used to encourage deployment around the world, and progress towards meeting targets. The economics of offshore energy projects are discussed, along with risks that projects face and the types of finance which are available. A final section turns to barriers - both technical and non-technical (including environmental, health and safety, skill related, supply chain and more) - and in all cases suggests how to mitigate and remove these barriers. Highly illustrated in full colour, this is an indispensable resource for anyone - whether in industry, policy or academia - looking to learn more about how deployment of offshore renewable energy technologies can be encouraged.

This Safety Guide provides recommendations on the operating organization and on personnel for research reactors to meet the relevant requirements of IAEA Safety Standards Series No. SSR-3, Safety of 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. This Safety Guide is a revision of IAEA Safety Standards Series No. NS-G-4.5, which it supersedes.

The ageing of structures, systems and components is one of the major challenges faced by nuclear fuel cycle facilities worldwide. This publication is intended to provide information on methods, approaches, practices and strategies for ageing management of nuclear fuel cycle facilities. It provides practical information on the establishment of effective ageing management programmes for nuclear fuel cycle facilities in the operational stage and on ageing management considerations in different stages in the lifetime of a nuclear fuel cycle facility. It also addresses the interface of ageing management with other technical areas and programmes, including maintenance, periodic testing and inspection, equipment qualification and configuration management. Best practice examples on how Member States are addressing ageing issues in nuclear fuel cycle facilities are also provided in this publication.

The transport of radioactive material is an essential activity worldwide. To ensure the protection and safety of people, property and the environment, appropriate regulations for the safe transport of radioactive material, both at the national level and at the international level, are necessary. Competent authorities regulate the transport of radioactive material through the application of national regulations, which should be consistent with relevant international regulations. This Safety Guide provides recommendations on actions that competent authorities should take to ensure compliance with the applicable regulations for the safe transport of radioactive material.

Probabilistic methods are increasingly being used to complement deterministic methods in assessing the safety and ensuring the reliability of research reactors. Addressing features specific to research reactors, this publication suggests a practical approach for the development and implementation of a project using probabilistic methods in terms of objective, scope, data and modelling, as well as the application of results to enhance safety and reliability. This publication is intended to be used by operating organizations, regulatory bodies and technical support organizations when performing or reviewing research reactor assessments in which probabilistic methods are applied. It will ideally be read in conjunction with relevant IAEA Safety Standards Series publications and technical guidelines for safety analysis, operation and maintenance, and component reliability data for research reactors.

This Safety Guide provides specific recommendations on establishing a programme and organization for commissioning of research reactors to meet the relevant requirements of IAEA Safety Standards Series No. SSR-3, Safety of Research Reactors. It covers the commissioning stages, procedures, reports and documentation and provides guidance for commissioning of new experimental devices and modifications. 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. This Safety Guide is a revision of IAEA Safety Standards Series No. NS-G-4.1, which it supersedes.

This Safety Guide provides specific recommendations on the safety of uranium and plutonium mixed oxide (MOX) fuel fabrication facilities. The potential hazards of a MOX fuel fabrication facility are release of actinides, increased radiotoxicity due to trans-uranium actinides, and nuclear criticality. The toxicity of plutonium is high and therefore it is important that best practices be employed at all stages of the fabrication of MOX fuel, and that plutonium be handled, processed, treated and stored safely. The revised Safety Guide reflects current operational practices at MOX fuel fabrication facilities. The recommendations in this publication are aimed primarily at the operating organizations of fuel fabrication facilities, regulatory bodies and designers.

This Safety Report provides practical guidance to governments, regulatory bodies, other relevant competent authorities, and building and construction material industries on setting up arrangements for regulatory control relevant to building and construction materials that give rise to radiation exposures at any step in their life cycle. These steps would include raw material production, manufacturing, supply and end use. It also considers the responsibilities of the suppliers of raw, waste or recycled materials for incorporation into building or construction materials, and it covers verification programmes for building and construction materials prior to their use as well as in completed construction projects.

With rapidly advancing digital technologies, smart devices are increasingly used in nuclear power plants. These smart devices can be implemented as separate or standalone field components or embedded as components in other equipment or systems and can be used to increase plant reliability, enhance safe operation and improve testing and monitoring functions. However, the use of smart devices may potentially introduce new hazards, vulnerabilities and failure modes. The safety aspects and design criteria associated with the safe use of industrial commercial smart devices in systems important to safety considered in this publication include: functional suitability and the evidence required to demonstrate this suitability, quality, qualification, the consideration of certification by non-nuclear organizations using non-nuclear standards, and aspects affecting integration of the smart device into existing systems in order to ensure that the smart device will retain its suitability for the required lifetime.

This Safety Guide considers the application of a graded approach throughout the lifetime of a research reactor (site evaluation, design, construction, commissioning, operation and preparation for decommissioning), including utilization and experiments that are specific features of research reactor operation. A major aspect of this Safety Guide involves the use of a graded approach in the application of the safety requirements for the design and operation of research reactors, so that the fundamental safety objective to protect people and the environment from harmful effects of ionizing radiation is achieved. It is intended for use by operating organizations, regulatory bodies and other organizations involved in the design, construction and operation of research reactors. This Safety Guide is a revision of IAEA Safety Standards Series No. SSG-22, which it supersedes.

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.

This Safety Guide provides specific recommendations on core management and fuel handling for research reactors, including handling and storage of fresh fuel, irradiated fuel, core components and neutron sources, 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. This Safety Guide is a revision of IAEA Safety Standards Series No. NS-G-4.3, which it supersedes.

This Safety Guide provides specific recommendations on the safety of uranium fuel fabrication facilities and describes the actions, conditions and procedures for meeting safety requirements. It deals specifically with the handling, processing and storage of low enriched uranium that has a uranium 235 concentration of no more than 6%, derived from natural, highly enriched or reprocessed uranium. This publication is a revision by amendment of IAEA Safety Standards Series No. SSG-6. It addresses the new safety requirements established by IAEA Safety Standards SSR-4, Safety of Nuclear Fuel Cycle Facilities, which incorporates the lessons learned from the accident at the Fukushima Daiichi nuclear power plant.

This Safety Guide, a revision of IAEA Safety Standards Series No. SSG-5, was initiated to provide recommendations on site evaluation, design, construction, commissioning, operation and preparation for decommissioning of conversion facilities and uranium enrichment facilities to meet the applicable requirements established in IAEA Safety Standards No. SSR-4, Safety of Nuclear Fuel Cycle Facilities, which incorporates the lessons learned from the accident at the Fukushima Daiichi nuclear power plant. The revised Safety Guide also reflects current operational practices at conversion facilities and uranium enrichment facilities. The recommendations in this publication are aimed primarily at operating organizations of conversion facilities and uranium enrichment facilities, regulatory bodies and designers.

Written for use by operating organizations of nuclear power plants and regulatory bodies, this Safety Guide provides specific recommendations on maintenance, testing, surveillance and inspection to ensure that the levels of reliability and availability of all structures, systems and components important to safety remain in accordance with the assumptions and intent of the design, and also that the safety of the plant is not adversely affected after the commencement of operation. The publication covers the establishment and implementation of preventive and corrective maintenance programmes; testing surveillance and inspection; the repair of defective plant equipment; the provision of related facilities and equipment; procurement; and generating and retaining records of maintenance activities.

The recommendations provided in this Safety Guide are aimed primarily at operating organizations of nuclear power plants and regulatory bodies. It covers the concept of operational limits and conditions (OLCs), their content as applicable to nuclear power plants, and the responsibilities of the operating organization for their establishment, modification, compliance and documentation. Operating procedures (including emergency operating procedures and severe accident management guidelines) to support the implementation of the OLCs and to ensure their observance are also within the scope of this Safety Guide.

Aimed primarily at regulatory bodies and the operating organizations of nuclear power plants, this Safety Guide provides recommendations on controlling activities relating to modifications to nuclear power plants. It covers modifications relating to plant configuration and to the operating organization, as well as temporary modifications. The responsibilities of the operating organization for the design, safety assessment and review, control, implementation and testing of these modifications are also within the scope of this Safety Guide as are the repair and replacement of equipment and components as part of the maintenance of the plant leading to new components.

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.

This publication has been developed to assist IAEA Member States in establishing and maintaining regulatory control through notification, authorization, inspection and enforcement in relation to facilities and activities with radiation sources, in order to achieve the fundamental safety and security objectives. The publication addresses the implementation of the requirements for safety and security in a harmonized way, taking into account differences in the requirements as well as differences in States' regulatory infrastructures. For example, in some States the same regulatory body is responsible for the control of safety and security, while in others, safety and security are controlled by separate regulatory bodies. A harmonized approach for notification, authorization, inspection and enforcement is intended to improve the efficiency and effectiveness of regulatory control through concurrent inspection for safety and security.

Aimed primarily at operating organizations of nuclear power plants and regulatory bodies, this Safety Guide covers the safety objective of core management and the basic tasks of the core management programme. The receipt of fresh fuel, storage and handling of fuel assemblies and core components, the loading and unloading of fuel assemblies and core components, and the insertion and removal of other reactor materials are within the scope of this Safety Guide. The publication also covers the preparations for the dispatch of irradiated fuel from the site.

Aimed primarily at operating organizations of nuclear power plants (NPPs) and regulatory bodies, this Safety Guide provides specific recommendations to ensure that operations in NPPs are conducted in a safe, effective, thorough and professional manner. It identifies the main responsibilities and operating practices in relation to such safe operation. The structure of the operations department, which is the part of the operating organization responsible for the conduct of operations of an NPP is addressed. Also addressed are the setting of high standards of performance and making safety related decisions in an effective manner, conducting control room activities in a thorough and professional manner and maintaining a nuclear power plant within the established operational limits and conditions.