Fatigue is a major element in time limited ageing analysis for long term operation of nuclear power plants (NPPs). It is important to understand how cracks occur and grow as a result of fatigue, and then assess fatigue failure. In the design and operating phase of NPPs, it is essential to consider the concurrent loadings associated with the design transients, thermal stratification, seismically induced stress cycles, and all relevant loads due to the various operational modes. After repeated cyclic loading, crack initiation can occur at the most highly affected locations if sufficient localized micro-structural damage has accumulated. This publication provides practical guidelines on how to identify and manage fatigue issues in NPPs. It explains the mechanism of fatigue, identifies which elements are the major contributors, and details how fatigue can be minimised in the design phase for new NPPs.

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.

Flexible operation and related power changes can have a direct impact on fuel integrity through pellet–cladding interaction/stress corrosion cracking (PCI/SCC) phenomena, which could lead to fuel failures in certain conditions. For some anticipated operational occurrences that affect fuel with small PCI/SCC margins, the fuel failures caused by PCI/SCC cannot be assumed to be benign, and a significant radiological source term may be generated. This publication provides an overview of PCI/SCC studies and reports on the progress made since the early 2000s, based on presentations and discussions at a related IAEA technical meeting held in October 2019.

This publication explains the concepts of quality assurance and quality control. It provides examples, illustrated by good practices, of their implementation within the processes of the management systems of nuclear facilities and describes how they are managed through interfaces with suppliers and subcontractors. The publication discusses the elements of a management system relevant for the quality assurance and quality control functions, such as the generation and retention of documented information. The information presented will help in ensuring the safe and economic operation of nuclear facilities and provide a neutral technical basis for dialogue between government bodies, regulators, plant operators and suppliers when dealing with management system, quality assurance and quality control issues.

The Fuel Incident Notification and Analysis System (FINAS) is jointly operated by the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organization for Economic Co-operation and Development (OECD/NEA). The system is an important tool for international exchange of operating experience from nuclear fuel cycle facilities. FINAS reports contain information about events of safety significance that have occurred at nuclear fuel cycle facilities and describe the root causes and lessons learned from the events. This publication provides a summary of the operating experience feedback from the events reported to FINAS since it was launched in 1992. The publication has a focus on the root causes, lessons identified, and corrective actions taken to prevent the occurrence of similar events. Reference to other publications that cover nuclear fuel cycle facilities’ events as well as a description of the operating experience programmes of these facilities is included. The publication is intended to be used by nuclear fuel cycle facilities’ operators, regulators, and designers.

With the increased level of investigation into uranium deposits in recent years, a wealth of new information has become available, which has made it possible to investigate some of the least understood aspects of uranium metallogeny. This publication defines a new classification scheme, which is simple and descriptive, but flexible enough to encompass the recent advances in our understanding of uranium geology and deposit genesis. It contains improved definition of the deposit types, supported by type examples of those deposits for which good data are available, but not well described in previous literature. Along with the descriptive information, new data on uranium resources available for each deposit type are also provided.

The World Distribution of Uranium Deposits (UDEPO) is a database on technical, geographical and geological characteristics of worldwide uranium deposits. The current version presents and describes modifications made since 2009. It presents a preliminary statistical and tabular analysis of the data for the first time, with a view to ensuring that the data is robust enough to serve as a basis for more sophisticated analysis in the future. This is supported by a detailed explanation of the structure of the database to better understand the nature of the data as a form of metadata. Furthermore, some basic graphical representations of the statistical and spatial distribution of the database is presented for the first time.

This publication presents the results and conclusions of an international research collaboration devoted to gaining a better understanding of the physics of Accelerator Driven Subcritical Systems (ADS), with particular emphasis on using low enriched uranium (LEU) fuel. The publication contains information on nine ADS facilities, including descriptions of the hardware deployed, experiments conducted, computational resources and procedures used in the analyses, principal results obtained, and conclusions drawn from the knowledge gained as a consequence of this work. It is intended to provide information for users of ADS systems and those involved in the design of new ADS facilities to use LEU fuel and in the conversion of some existing facilities from using highly enriched Uranium (HEU) to LEU.

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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.

On request, the IAEA performs comprehensive audits of radiotherapy programmes to assess the whole process, including aspects such as organization, infrastructure and clinical and medical physics components. The objective of a comprehensive clinical audit is to review and evaluate the quality of all components of the practice of radiotherapy at the institution, including its professional competence, with a view to quality improvement. A multidisciplinary team, known as Quality Assurance Team in Radiation Oncology (QUATRO), comprising a radiation oncologist, a medical physicist and a radiation therapist, are required to carry out the audit. The present publication provides revisions of the QUATRO guidelines published in 2007, by incorporating new procedures relevant to newer technologies and modalities that have become routinely used in radiotherapy centres in the interim period.

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 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.

This Safety Guide identifies the main objectives and responsibilities of the operating organization for the recruitment, qualification and training of personnel for new and existing nuclear power plants to establish and maintain a high level of competence of personnel and to ensure safe operation of the nuclear power plant. This publication can also be used as a guide for the recruitment, training and qualification of personnel for nuclear installations other than nuclear power plants.

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.

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.

This Safety Guide provides recommendations on the safety assessment for research reactors in the authorization process, and on performance of safety analysis and preparation of the safety analysis report. It also incorporates the relevant lessons learned from the accident at the Fukushima Daiichi nuclear power plant and elaborates guidance on interfaces between nuclear safety and nuclear security. The recommendations in this Safety Guide are intended for operating organizations of research reactors; it can also be used by designers performing a safety assessment for a research reactor. Furthermore, this guide provides useful guidance for regulatory bodies performing a review and assessment of submitted safety analysis reports as an important document within authorization process. This Safety Guide is a revision of IAEA Safety Standards Series No. SSG-20, which it supersedes.

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 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.

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.

This publication gives practical information and examples on safety analysis principles and methods as well as the contents of licensing documentation needed to support application of IAEA safety standards to nuclear fuel cycle facilities. A systematic methodology is presented, covering the establishment of acceptance criteria, hazard evaluation, identification of postulated initiating events, analysis of accident sequences and consequences. Information is also provided on application of the results of the safety analysis in the design and operational phases, and on appropriate management system processes. The publication applies to all lifetime stages of relevant facilities and for modifications and upgrades. The information presented may be used for periodic safety reviews and consideration of extended lifetime of facilities. With respect to licensing documentation, the publication provides indicative contents and format of the safety analysis report as a higher level document that incorporates the information required at various steps in the licensing and re-licensing process.

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.

Artificial sources of radiation are commonly used in the manufacturing and service industries, research institutions and universities, and the nuclear power industry. As a result, workers can be exposed to artificial sources of radiation. There are also a significant number of workers, such as underground miners and aircrew, who are exposed to naturally occurring sources of radiation. This publication, prepared in collaboration with the International Labour Organization, and with reference to IAEA Safety Standards Series No. GSR Part 3 provides guidance for individuals and organizations on the assessment of prospective cancer risks due to occupational exposure to ionizing radiation for prevention purposes. It describes cancer risk assessment theory, models and methodologies, and offers practical examples of carrying out these assessments.

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.