Developing a nuclear power programme is a major undertaking requiring careful planning and preparation. This publication provides guidance for Member States that with to assess the resources required for the development of the infrastructure needed for a nuclear power programme. Resource estimates are presented in person years, to account for economic differences across countries, in terms of labour costs, which may vary significantly. The data are presented in sufficient detail that they can also be used by countries that have decided to expand their nuclear programme after a long period without building any new nuclear power plants.

Requirements for the safe transport of radioactive material are established in IAEA Safety Standards Series No. SSR-6 (Rev. 1), Regulations for the Safe Transport of Radioactive Material, 2018 Edition. Packages intended for the transport of radioactive material have to be designed to meet applicable national and international regulations. For package designs that require approval by a competent authority, the documentary evidence of compliance with the applicable regulations is commonly known as package design safety report (PDSR). For package designs that do not require competent authority approval, a PDSR would also be an appropriate form of documentary evidence of compliance with the Transport Regulations. This Safety Guide provides recommendations on the preparation of a PDSR to demonstrate compliance of a package design for the transport of radioactive material with the Transport Regulations. This Safety Guide is intended for use by applicants for approval of package designs (when package designs are subject to competent authority approval) as well as by package designers and/or consignors (when package designs do not require competent authority approval). Regulators will benefit from the common structure for the competent authority assessment process, and designers and consignors will find a consistent approach to justify the compliance of a package design with the regulatory requirements.

This publication provides practical guidance and information to Member States on how to manage nuclear safety knowledge at the national level, beyond the boundaries of individual organizations. It describes the underlying concepts, challenges and available approaches and tools, as well as summarizing the experience gained by Member States to date. The publication is in line with the ultimate objective of all nuclear safety knowledge management activities, which is to sustain and improve the competence of individuals and the capacity of organizations or countries to use such knowledge effectively and responsibly.

This Safety Guide provides specific recommendations on protection against internal and external hazards in the operation of nuclear power plants. It provides new or updated recommendations 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.

Member States continue to request guidance on introducing nuclear power to their power production strategy. This revised publication presents developments in managing siting activities since the 2012 edition. It provides the updated methodology and framework to assist Member States in site identification, selection, evaluation and licensing, and discusses aspects including nuclear safety and security, technology and engineering, economics and cost, land use planning and preparation, socioeconomic impacts and involvement of stakeholders. The intended users include decision makers, senior managers and other technical specialists involved in siting and site evaluation. It is also relevant for Member States seeking to expand existing nuclear power programmes.

This publication describes the purpose and scope of the INPRO service Analysis Support for Enhanced Nuclear Energy Sustainability (ASENES) and its potential benefits to Member States. The publication highlights the links between this service and overall technical support to Member States for the planning and development of nuclear energy, and explains how it integrates with other IAEA services supporting knowledgeable decision making on nuclear power. An overview of analytical tools developed by INPRO for this purpose is also provided.

This Safety Guide provides recommendations and guidance on fulfilling the requirements of IAEA Safety Standards Series No. GSR Part 3, Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards, for ensuring radiation protection and safety of radiation sources in medical uses of ionizing radiation with regard to patients, workers, carers and comforters, volunteers in biomedical research, and the public. It covers radiological procedures in diagnostic radiology (including dentistry), image guided interventional procedures, nuclear medicine and radiotherapy. Recommendations and guidance are provided on applying a systematic approach to ensure that there is a balance between being able to utilize the benefits from medical uses of ionizing radiation and minimizing the risk of radiation effects to people.

Engaging with stakeholders is an essential part of any complete nuclear programme. Involving stakeholders in decision making processes, even those stakeholder groups that do not have a direct role in making those decisions, can enhance public confidence in the application of nuclear science and technology and strengthen communication among the key organizations in a nuclear programme. This publication provides theoretical and practical guidance on the development and implementation of stakeholder engagement programmes and activities. The key principles of stakeholder engagement are identified in it. It also includes tools such as templates to help establish a stakeholder engagement programme and identify associated activities, including tools for stakeholder analysis. The guidance provided can be further developed and adjusted to each specific type of facility, moment in its life cycle, and/or the group of stakeholders with which to engage. The publication demonstrates the importance of stakeholder engagement throughout the life cycle of all nuclear facilities, including operating and new reactors, all aspects of the nuclear fuel cycle, from uranium mining to spent fuel and radioactive waste management, decommissioning, and non-power applications.

A properly established governmental, legal and regulatory framework for safety provides for the effective regulatory control of facilities and activities with radiation sources. An important aspect of a regulatory framework is to ensure that the implementation of the regulatory programme is commensurate with the radiation risks associated with facilities and activities, in accordance with a graded approach. This publication provides practical guidance on the application of a graded approach in regulating the safety of radiation sources. Examples of applying this approach in some Member States are included. The proposed methodologies promote a systematic and consistent approach to regulating in accordance with the IAEA safety standards.

This publication provides a comprehensive summary of experiences and results collected at a series of technical meetings of Member States currently operating CANDU-type nuclear power plants. Special emphasis is placed on supporting future harmonization in the regulatory framework, level 1 PSA methodologies and tools and level 1 PSA scope. In addition, information is shared on actions undertaken in response to lessons learned from the Fukushima Daiichi accident.

This publication provides guidance to States, competent authorities and operators on appropriate nuclear security measures during each stage in the lifetime of a nuclear facility, from initial planning of the facility through to its final decommissioning. The publication addresses effective nuclear security in the transition between stages and applies to the nuclear security of nuclear material and nuclear facilities throughout the lifetime of all types of nuclear facilities. Although focused on nuclear power, the guidance contained in this publication may be useful for States developing nuclear programmes with other types of facilities, including those for research and development.

As part of the IAEA programme on International Generic Ageing Lessons Learned (IGALL), this publication provides a summarized description of internationally accepted practices. Examples of the national approaches to ageing management for the specific periods of extended shutdown, delayed construction and post final shutdown as applied in the nuclear power plants of participating IGALL Member States are presented. In addition, some of the information is also applicable for the evaluation of ageing effects prior to and after restarting operation. The publication complements existing IAEA publications on ageing management approaches of Member States during normal operation and is intended for use by regulatory bodies, operating organizations, manufacturers, designers and technical support organizations.

This publication documents the results of an IAEA coordinated research project (CRP)on the application of computational fluid dynamics (CFD) codes for nuclear power plant design. The main objective was to benchmark CFD codes, model options and methods against CFD experimental data under single phase flow conditions. This publication summarizes the current capabilities and applications of CFD codes, and their present qualification level, with respect to nuclear power plant design requirements. It is not intended to be comprehensive, focusing instead on international experience in the practical application of these tools in designing nuclear power plant components and systems. The guidance in this publication is based on inputs provided by international nuclear industry experts directly involved in nuclear power plant design issues, CFD applications, and in related experimentation and validation highlighted during the CRP.

Radiotherapy can be delivered with different types of machine, such as external beam high energy radiation machines, kilovoltage machines and brachytherapy equipment. Variation in the incidence of different cancer types, the complexity and cost of treatment technologies, and differences in local social, economic and physical circumstances are all factors that influence technology acquisition, purchase and implementation. This publication addresses one of the many factors, associated with the planning of a new radiotherapy facility or the upgrade of an existing one – the selection of a high energy (megavoltage) radiotherapy machine. The two main high energy machine types are medical linear accelerators (linacs) and cobalt?60 machines. Although both treatment modalities have been compared extensively in the relevant literature, very few publications describe all the issues to consider when choosing a megavoltage machine. This publication puts all appropriate questions into context and provides information for non?technical administrators and decision makers, and for professionals directly involved in treating patients.

This publication reports on the DACCORD project, which supports Member States in preparing preliminary cost estimates for the decommissioning of research reactors. The report is of particular benefit to programmes with limited decommissioning experience. Costing projects for the decommissioning of research reactors can be broad in scope with many possible inputs and influences that require due consideration in developing the estimate. The publication provides information on unit factors for research reactor decommissioning and a basis for estimating uncertainties and contingencies and for assessing the impact of decommissioning planning and characterization activities. It also addresses the use of the CERREX?D2 (Cost Estimate for Research Reactors in Excel) software code, developed by the IAEA to enable non?specialist users to develop preliminary cost estimates for decommissioning.

This Safety Report provides detailed information on ageing management programmes and time limited ageing analyses to manage existing and potential ageing effects and degradation mechanisms of structures, systems and components (SSCs) that are important to the safety of nuclear power plants. It has been written to assist operating organizations and regulatory bodies by specifying a technical basis and providing practical guidance on managing ageing of mechanical, electrical and instrumentation and control components, and civil structures. It also provides a common, internationally recognized basis on what constitutes an effective ageing management programme, a knowledge base on ageing management for design of new plants and design reviews, and a roadmap to available information on ageing management.

A number of IAEA Member States generate relatively small quantities of radioactive waste and/or disused sealed sources in research or in the application of nuclear techniques in medicine and industry. This publication presents a modular approach to the design of waste processing and storage facilities to address the needs of such Member States with a cost effective and flexible solution that allows easy adjustment to changing needs in terms of capacity and variety of waste streams. The key feature of the publication is the provision of practical guidance to enable the users to determine their waste processing and storage requirements, specify those requirements to allow the procurement of the appropriate processing and storage modules and install and eventually operate those modules.

Fusion energy has potential to contribute to meeting global demand for sustainable energy Increasingly, progressive fusion enterprises are seeking new pathways for the commercialization of the technology, bringing fresh ideas and different perspectives. This publication is a summary of an IAEA Workshop on this topic, outlining the main elements for the development of alternative commercialization pathways for fusion energy systems in the coming decades, bringing together expert opinions from the diverse range of disciplines that are essential to fusion's commercial success. It highlights several critical aspects to consider for new pathways and provides an outline of a roadmap for their development.

This Safety Guide, prepared jointly by the International Atomic Energy Agency (IAEA) and the International Labour Organization (ILO), provides guidance on fulfilling the requirements of the International Basic Safety Standards (IAEA Safety Standards Series No. GSR Part 3) with respect to occupational exposure. It provides general guidance on the development of occupational radiation protection programmes as appropriate for the sources of radiation likely to be encountered in the workplaces in question to fulfil the management's responsibility for protection and safety. Detailed guidance is also provided on the monitoring and assessment of workers' exposure due to external radiation sources and from intakes of radionuclides. The Safety Guide reflects the current internationally accepted principles and recommended good practices in occupational radiation protection, with account taken of the conceptual changes and technological enhancements that have occurred over the past decade.

This publication summarizes the reviewed information distributed in previous IAEA publications and provides an up to date, overall picture of the management of disused sealed radioactive sources (DSRSs) based upon the current status and trends in this field. It incorporates the most recent experience in source management, including newly developed techniques used for DSRS conditioning and storage. Problems encountered and lessons learned are also highlighted in the publication in order to help avoid the mistakes commonly made in the past in managing disused sources.

The identification and assessment of threats provides an essential basis for the selection, design, and implementation of nuclear security measures. For nuclear material and other radioactive material that is under regulatory control, and associated facilities and activities, the results of this identification and assessment are expressed as a design basis threat or representative threat statement describing the intentions and capabilities of potential adversaries against which the materials and associated facilities and activities are to be protected. An Implementing Guide was issued in 2009 under the title of Development, Use and Maintenance of the Design Basis Threat which was updated and revised. The result of this revision is the current publication. It provides a stepbystep methodology for conducting a national nuclear security threat assessment including both physical and computer security aspects, and for the development, use and maintenance of design basis threats and representative threat statements.

Since the 1970s, the IAEA has been involved in the analysis of fuel failures in water cooled reactors in normal (nonaccident) operational conditions. This updated version of IAEA Nuclear Energy Series No. NFT2.1 provides information on all aspects of fuel failures in current nuclear power plant operations. It summarizes fuel failure occurrences and their mechanisms and root causes, as well as fuel failure prevention and management in plant operation for 97% of light and heavy water cooled nuclear power units operated worldwide during the period 2006-2015. Data on fuel failures from 1987 to 2006 extracted from three previous IAEA fuel failure reports are included and analysed in the present publication, together with the 2006-2015 fuel failure data, to reveal long term tendencies in fuel performance. In addition to fuel rod leakers, fuel structural damages and other fuel assembly issues are considered in the report.

The need has arisen for a comprehensive handbook for engineers faced with problems of radiation shielding design. Although there are several excellent books on shielding, they either do not give enough consideration to the many practical design problems, or are limited to special aspects of the subject. Recognizing the universal need, the International Atomic Energy Agency decided to sponsor the publication ofthe present Engineering Compendium on Radiation Shield ing. At the first editorial discussions it was agreed that, if such a book were to be undertaken, it would be appropriate not only to create a useful design tool for the practising engineer but also to include well-referenced basic data for the research worker. Although trying to keep the book down to a reasonable size, the editors have aimed at a complete presentation of the subject, covering and linking both the tech nology and the science of shielding. Efforts to make terms and definitions consistent throughout have been only partially successful, owing to the continuing development of new ideas. However, inconsisten cies that could not be eliminated are identified whenever possible."

This publication provides a global overview of the status of spent fuel and radioactive waste management programmes, inventories, current practices, technologies and trends. It presents information on national arrangements for the management of spent fuel and radioactive waste, and on current waste and spent fuel inventories and their future estimates. Achievements, challenges and trends in the management of spent fuel and radioactive waste are also addressed. This second edition has been developed with a basis of national profiles submitted by Member States, complemented with openly available Joint Convention National Reports. The data reported are fully dependent on the input from the States and by the assumptions made to transform these data into the waste classes defined in IAEA Safety Standards Series No. GSG?1, Classification of Radioactive Waste.

The focus of this publication is on collecting current practices in Member States related to design extension conditions (DECs) with core melting. The information provided is based on the feedback from technical experts from Canada, France, Finland, India, the Islamic Republic of Iran, the Russian Federation, and the United States of America. There is, however, still no common understanding of DECs due to the complexity of phenomena and insufficient experimental data. This publication identifies current approaches of IAEA Member States with active nuclear power programmes and discusses the regulatory perspective and technical rationale. It attempts to find common practices and possible areas for harmonization of the main rules related to the analysis of DECs with core melting for new water cooled reactors, including their selection for the safety demonstration.