Providing a comprehensive overview of project management for the construction of research reactors, this publication gives guidance to Member States on the best practices that will assist in the realization of that phase of a research reactor deployment project. Member States planning to embark on a research reactor programme together with a nuclear power programme may also refer to this publication to ensure that the approach and methodology for the implementation of both is harmonized, efficient and effective.

Protection of the environment is one of the cornerstones of sustainable development, a key consideration for Member States embarking on new nuclear power programmes. National requirements and international instruments increasingly reflect this concern and for the provision of opportunities for interested parties and stakeholders to be involved in decision-making processes. This new edition provides valuable guidance to Member States on issues related to environmental protection when considering a new nuclear power plant. It aligns more closely with the phased approach and takes into account Revision 1 of IAEA Nuclear Energy Series NG-G-3.1 and highlights the interface with other infrastructure issues. It also considers lessons learned from the 30 Integrated Nuclear Infrastructure Review (INIR) missions conducted to date, and ensures consistency, and alignment of approaches and terminology with other relevant IAEA publications. This publication is primarily intended for Member States who are considering or embarking on new nuclear power programmes, and specifically the decision makers and technical specialists who are involved in environmental protection.

The use of decontamination methods and techniques are complex, and an integrated assessment of technical performance, environmental factors, and costs is necessary for selection where large decontamination projects in the Nuclear Industry requires a combination of processes. This publication focusses on decision making in the planning of nuclear and radiological decontamination projects and provides guidance on the selection of the most appropriate approach. It includes consideration of relevant factors and how individual factors are weighed, merged and combined leading to an integrated decision on the preferred approach. The publication is expected to be of use to all those involved in the planning of a decontamination project.

The decision to establish a nuclear power programme is a significant undertaking by any country. Such a decision should be based on a commitment by the government to use nuclear power safely, securely and peacefully. This commitment requires establishing a sustainable national infrastructure including robust safeguards infrastructure supporting the functions of the State system of accounting for and control of nuclear material (SSAC). The IAEA has developed the Milestones Approach to help Member States embarking on nuclear power to plan and develop the necessary infrastructure in a phased way. Safeguards is one of the 19 infrastructure issues described in the Milestones Approach. The primary objective of this publication is to provide guidance and references for safeguards related activities that need to be carried out during each of the three phases of nuclear power infrastructure development in line with the nuclear power programme implementation. This publication includes several case studies from different countries on how they developed their national safeguards infrastructure to meet the requirements of their nuclear power programmes.

The terms for describing advanced nuclear power plants (NPPs) need to conform to the broad, general, common understanding by the public as well as by the technical community. This publication is a revision of IAEA-TECDOC-936 incorporating developments and initiatives since 1997 in the areas of advanced, evolutionary, and innovative nuclear reactor designs, description of design development phases, inclusive of relevant safety and regulatory terminology, consistent with current IAEA safety standards and glossaries. The objective of this publication is to provide Member States with up-to-date terms for describing advanced NPPs, to draw distinctions between design phases reflecting the maturities of designs, and to clarify definitions of commonly used terms in describing advanced NPPs.

Nuclear cogeneration to produce electricity and process heat for nonelectric applications such as desalination, district heating or cooling or hydrogen production can play an important role in reducing dependence on fossil fuels. The implementation of nuclear cogeneration projects is inherently complex and such projects require a clear understanding of actions and responsibilities during the design, operation and management phases. This publication focuses on analysing the requirements and responsibilities of users and vendors and correspondence between them through the life cycle to of a nuclear cogeneration project, highlighting experience and lessons learned from retrofit and new build projects.

Integrated risk management (IRM) is particularly important during the preparation and construction phases of a nuclear power plant (NPP) and anticipates the risks that could arise during the operation and decommissioning phases. This publication is designed to enhance stakeholders' understanding of the fundamental processes, procedures, and methods for IRM. Practical guidelines are provided and best practices shared. The importance of having appropriate risk management policies, especially when considering the various contractual and organizational arrangements in different construction entities, operating organizations and Member States is emphasized. Tables are provided throughout the publication to indicate the causes of risks and their impacts on the applicable NPP or project. Economic evaluation techniques are also introduced. Member States contemplating expanding their existing nuclear power plant fleets can be expected to benefit from this publication, but it will likely be most valuable for Member States newly embarking upon a nuclear power programme.

This publication, which draws upon the outcome of an IAEA coordinated research project, presents methodologies for assessing pipe failure rates in advanced water cooled reactors (WCRs), including a comprehensive review of good practices for the assessment of piping reliability parameters for advanced WCRs. Good practices are those processes and analytical tasks that would be expected in piping reliability analysis in order for the results to be realistic representations of piping structural integrity. This publication builds on technical insights that have been obtained using different methodologies when applied in multiple analytical contexts and responding to the requirements of different national codes and standards. It provides Member States with a strong technical basis for establishing design and plant centric piping reliability parameters for input into probabilistic safety assessment studies, in-service inspection programme development, and operational support. Additionally, an objective evaluation and inter-comparison of methods used in participating Member States is outlined leading to a harmonization of the practices relevant to newly deployable advanced WCRs.

This publication aims to outline credible technical options for managing separated plutonium. There is no attempt to rank or rate any of the options, instead the intent is to inform the reader of the technical merits of the various options and the state of their development. It is primarily focused on Member States that have adopted a closed fuel cycle policy but can also be of value to other Member States, specifically their decision makers and other stakeholders involved in potential future nuclear fuel cycles, by informing them on life cycle options and energy policy.

Sites with radioactive contamination may require action to protect people and the environment and to enable transition to a different future use. To support environmental management of these sites, this publication presents a process to determine the “end state” of the site to be remediated or being remediated, and implications for the site future use and necessary controls. The approach is intended to assist those responsible for a site in making an informed and transparent decision on what is the mutually agreed end state. It provides a common basis for all stakeholders involved in the decision-making process, who are working on achieving consensus, so that the potential for misunderstanding is reduced.

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 minimized in the design phase for new NPPs.

Post-irradiation examination (PIE) is an indispensable step in the selection of new or improved research reactor fuel, and in the characterization and understanding of its in-core behaviour. This publication provides an introduction to PIE techniques. It describes a typical PIE process from intercycle inspections in the reactor pool or channel, to hot cell PIE, which is subdivided into non-destructive and destructive testing techniques with their typical output, advantages and drawbacks, and their applicability to understanding fuel irradiation behaviour. Much of the work presented in this publication originated from the research and development of new low enriched uranium research reactor fuels. Intended readers include research reactor operators, regulators and their technical support organizations, fuel developers and manufacturers, laboratory staff, and policy makers.