This publication provides detailed information on recent technical advancements and operational procedures achieved through the Coordinated Research Project (CRP) on “Use of Long-Lived Radionuclides for Dating Very Old Groundwater”. It covers field portable membrane gas extraction devices for sampling dissolved gases from groundwater aquifers, as well as a custom-built krypton purification system for purifying krypton from field-collected bulk gas samples. Additionally, the publication offers guidelines for selecting appropriate groundwater wells and sampling tools, as well as recommendations for proper sample handling and transportation. These guidelines are essential to ensure smooth field sampling, which is vital for accurate isotope analysis and data interpretation. This publication is primarily aimed at professionals in hydrology and environmental science, including researchers and practitioners in isotope hydrology. It is also a valuable resource for groundwater resource managers and policy makers who oversee water sustainability initiatives as well as academic institutions and research labs specializing in earth sciences. It can also benefit government bodies and international organizations focused on environmental policy and water resource management.

The IAEA facilitated the co-operation of research and development among its Member States on advancing the state-of-practice in uncertainty and sensitivity methodologies for severe accident analysis in water cooled reactors. The main objective was to consolidate the existing knowledge related to uncertainty propagation in severe accident analyses in boiling water reactors (BWRs), and to enhance the expertise of practitioners in this specialized field. This publication showcases contributions from eight institutions from seven Member States, detailing their utilized methods for uncertainty and sensitivity analysis in severe accidents for BWR designs.

This publication explores the variety of contracting and ownership approaches for a nuclear power plant, illustrated with recent case studies, to assist Member States in understanding the range of options available and the associated benefits and challenges of each approach. Regardless of the approach adopted, the requirements for the safe, secure and peaceful operation of a nuclear power plant remain the same. The challenge is to make sure that these requirements are adequately considered and addressed in Member State nuclear power programmes. This publication is a revision of IAEA-TECDOC-1750, Alternative Contracting and Ownership Approaches for New Nuclear Power Plants, published in 2014, which examined build–own–operate and build–own–operate–transfer models as well as regional approaches in relation to contracting and ownership.

Nuclear fuel cycle facilities (NFCFs) have played a major role in the development and application of nuclear technologies in various fields, including nuclear power and nuclear science and technologies for over seven decades. Approximately 70% of the operating NFCFs in the world are more than 30 years old, thus it is important that life management programmes are established and implemented. This publication provides practical information on factors affecting ageing and their consequences, and mitigating action required for nuclear fuel cycle facilities in the operational stage including modernization and refurbishing. It also provides the considerations for long term operation of a nuclear fuel cycle facility. The information in this publication will be useful to the operating organizations, regulatory bodies and other organizations involved in the design, construction, operation and management of nuclear fuel cycle facilities’ safety.

This is the 44th edition of Reference Data Series No. 2, which presents the most recent reactor data available to the IAEA. It contains summarized information as of the end of 2023 on power reactors operating, under construction and shut down as well as performance data on reactors operating in the IAEA Member States. The information is collected through designated national correspondents in the Member States and the data are used to maintain the IAEA's Power Reactor Information System (PRIS).

This report contains the 55th edition of the IAEA’s series of annual reports on operating experience with nuclear power plants in Member States. It is a direct output from the IAEA’s Power Reactor Information System (PRIS) and contains information on electricity production and overall performance of individual plants during 2023. In addition to annual information, the report contains a historical summary of performance during the lifetime of individual plants and figures illustrating worldwide performance of the nuclear industry. The design characteristics and dashboards of all operational nuclear power plants worldwide are also included.

This publication provides practical information on establishing and implementing regulatory inspection programmes for Nuclear Fuel Cycle Facilities (NFCFs). It covers the regulatory inspection process, the elements of a systematic regulatory inspection programme, and the interface of regulatory inspections with other functions and processes of the regulatory body. This publication is useful for regulatory bodies and their technical support organizations dealing with the regulatory inspection of NFCFs. The publication could also be useful for operating organizations in preparation for regulatory inspection, and for management review of the safety of NFCFs.

This publication describes the work undertaken by Working Group 7, Assessment of Fate and Transport of Radionuclides Released in the Marine Environment of the IAEA’s Modelling and Data for Radiological Impact Assessments (MODARIA II) programme (2016–2019). The work carried out was a natural continuation of that completed during the first phase of the IAEA’s MODARIA programme (2012–2015) by Working Group 10, Modelling of Marine Dispersion and Transfer of Radionuclides Accidentally Released from Land Based Facilities. In MODARIA II, the degree of complexity of the models used was increased in order to effectively consider additional processes, specifically uptake by biota, and the spatiotemporal scales of the simulations were also expanded. General information on the simulation of radionuclides in the marine environment using dispersion and transport models was compiled. This is intended for scientists in Member States considering development or adoption of models for radiological assessment following incidents or emergencies involving releases of radionuclides into the marine environment.

This publication developed by the International Nuclear Safety Advisory Group (INSAG) supplements its advice provided in INSAG-10 underscoring application of the principle of defence in depth in nuclear safety for small modular reactors and related emerging technologies. It is intended to stimulate discussion and to promote practical action at all levels to enhance safety of Small Modular Reactors (SMRs). INSAG provides recommendations on current and emerging nuclear safety issues to the IAEA, the nuclear community, and the public. The report is intended for use by governmental authorities and by the nuclear industry and its supporting organizations. In particular, the intended audience includes national decision makers for nuclear power programmes using small modular reactors (SMRs), researchers and designers in this field and nuclear and radiation safety experts.

The IAEA facilitated the co-operation on research and development among its Member States on the development and validation of computer codes for the design and safety analysis of nuclear power plants. The main objective of this effort was to bring together the current state-of­knowledge on uncertainty propagation in severe accident analyses that has been accumulated by experienced analysts with the aim of increasing the sophistication and competency of the practitioners in this field. This publication provides the contributions from four individual organizations from four Member States describing their employed uncertainty and sensitivity assessment methods applied in simulating the QUENCH-06 experiment performed at the Karlsruhe Institute of Technology (Germany) in December 2000. The QUENCH-06 experiment was designed to explore the behavior of nuclear fuel under oxidizing and quenching conditions during severe accident scenarios in light water nuclear reactors. Due to its comprehensive nature, this experiment was chosen as the benchmark for evaluating the performance of severe accident codes employed by participants in this coordinated research project. This publication is intended for nuclear engineers, researchers, code developers, experimentalists in nuclear energy fields, reactor vendors and developers, university professors and students, regulatory experts, and nuclear power plant planners.