This publication provides information and guidance on the establishment of a process for periodic safety review for research reactors, including preparation, conduct of the review and reporting of results. In addition, it covers the regulatory assessment of these results. The publication also provides information on the experience of Member States in establishing and implementing periodic safety reviews of research reactors, including implementation of reasonable and practical improvements based on these reviews.

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 and electrical instrumentation and control components, and civil structures. It also provides a common, internationally recognized basis of 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.

Experience shows that an assessment of the seismic capacity of an existing operating facility can be required for a number of reasons, for example identification of potential seismic vulnerabilities based on operating experience events or the periodic safety review programme. This publication covers the seismic safety evaluation programmes to be performed on existing nuclear installations in order to ensure that the required fundamental safety functions are available, with particular attention to the safe shutdown of reactors. It includes lessons learned based on the IAEA Action Plan on Nuclear Safety following the Fukushima Daiichi accident, and updated methodologies for seismic safety evaluation of nuclear installations.

This publication focuses on the medical management of individuals involved in radiation emergencies, especially those who have been exposed to high doses of ionizing radiation. Its primary objective is to provide practical information, to be used for treatment decisions by medical personnel during a radiation emergency. It also addresses general and specific measures for the medical management of individuals who have been internally contaminated with radionuclides. This publication is complementary to other publications developed by the IAEA in the medical area of radiation emergencies.

This publication gives practical information and examples of 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 relicensing process.

This Safety Report has been developed as part of the IAEA programme on occupational radiation protection to provide for the application of its safety standards in implementing a graded approach to the protection of workers against exposures associated with uranium mining and processing. The publication describes the methods of production associated with the uranium industry and provides practical information on the radiological risks to workers in the exploration, mining and processing of uranium. It is a compilation of detailed information on uranium mining and processing stages and techniques, general radiation protection considerations in the relevant industry, general methodologies applicable for control, monitoring and dose assessment, exposure pathways, and radiation protection programmes for a range of commonly used mining and processing techniques.

This Safety Report draws on the requirements of international standards and the recommendations of international organizations as well as on the scientific literature, together with direct experience from a number of IAEA Member States in relation to carrying out representative indoor radon surveys. The need for and the purpose of representative indoor radon surveys are discussed, as are the factors that must be considered in designing and carrying out such surveys. How the measurement data obtained from indoor radon surveys can be used to develop radon risk maps is also considered. While the Safety Report is focused specifically on national and regional surveys to evaluate average concentrations of radon in dwellings, many of the same considerations also apply to radon surveys for other types of buildings.

The technical approach described in this publication builds on the use of a single unit probabilistic safety assessment (PSA) and identifies considerations that are needed from the multi-unit perspective. This is the first attempt to expand the current PSA process to take account of multi-unit issues, and has been done by distilling lessons learned from the Fukushima Daiichi accident and other multi-unit events, and by reviewing previous PSAs and supporting research that have addressed the risks of multi-unit accidents. The publication provides a roadmap and methodology for performing a multi-unit PSA, proposes a set of site level risk metrics, and presents examples of approaches to resolve specific issues.

This Safety Report provides specific guidance on the management of project risks in decommissioning. The publication proposes a systematic and proactive approach to identifying, analysing, evaluating, and treating relevant project risks at strategic and operational levels, and provides examples of application of the proposed approach.

This publication provides information and a framework for Member States to conduct realistic safety evaluations for research reactors in terms of external events. The publication provides information with examples on the use of a graded approach, based on the radiological hazard that a facility poses to the environment, the public and workers, and takes into account the lessons from the Fukushima Daiichi accident. This publication supports the development of site specific guidelines for the actual design and safety assessment, and should be used in conjunction with the relevant IAEA safety standards. It can also be used as training material for research reactor staff and for a self-assessment of the vulnerability of existing structures to external events.

For proper planning and safe implementation of decommissioning of facilities, an accurate estimate of the radioactive inventory of the facility is needed (i.e. source term determination). The largest fraction of this inventory for nuclear power plants, research reactors and accelerator facilities is created by induced activation by neutrons or other particles (protons, electrons, ions). This publication provides information for facility operators and regulatory authorities involved in decommissioning planning and oversight of the process of assessment of the induced activation source term of a facility. It provides information on the selection and application of methodologies for the assessment of the induced activation source term for decommissioning purposes and provides an overview of the approaches and practices currently available.

This publication outlines the generic methodology for probabilistic safety assessment of nuclear power plants against external hazards. It integrates design, procedural, operational and human factors, and both protection and mitigation aspects that are essential for modelling a nuclear power plant response to an external hazard and to assess the associated risk. It specifically addresses the identification and screening of external hazards considering the impact on multi-unit plants.