This publication is the revision of IAEA-TECDOC-1732, Model Regulations for the Use of Radiation Sources and for the Management of the Associated Radioactive Waste. This publication provides information on the drafting of regulations and includes model regulations covering all aspects of the safe use of radiation sources and the safe management of the associated radioactive waste. The Model Regulations presented in this TECDOC are intended to implement requirements established in the IAEA safety standards, in particular IAEA Safety Standards Series Nos GSR Part 3, Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards, and GSR Part 5, Predisposal Management of Radioactive Waste.

Lead-210 (Pb-210) dating can be used to understand depositional trends of contaminants in the coastal marine environment. Decades of research have been committed to optimizing the use of Pb-210 as an isotopic tool to date sediment layers, yet challenges in its application limit its full potential. This TECDOC uses real case studies from around the world to examine the challenges and assumptions in using the method, the scope of its use, discussion on model usage, and validation. The geographic diversity of the presented studies provides a snapshot of the effect of anthropogenic activities and the resulting organic, inorganic, and radioactive contaminants on our coastal oceans. This publication is intended for environmental scientists and marine managers.

Safe and sustainable uranium production requires comprehensive asset management guidelines, strategies, procedures and planning for uranium mines and processing facilities. This TECDOC offers guidance on management strategies and maintenance techniques for ageing uranium production cycle facilities. Based on industry best practices and international standards, it draws from the expertise and insights of industry professionals to consolidate knowledge on the life cycle asset management of uranium mines and processing facilities. This guidance is applicable to existing, new and ageing uranium production facilities and is intended for use by governmental organizations in Member States, regulatory bodies, and owners and operators of uranium mines and mills.

This publication provides specific methods and tools for the identification, development, selection, establishment and use of performance indicators (PIs) to measure and report on the implementation and effectiveness of knowledge management programmes to improve the overall performance of a nuclear organization. It captures examples that are applicable to the entire lifecycle of a nuclear organization. While the guidance is intended primarily for senior and middle level utilities management, the concepts and approaches are useful for all other nuclear organizations, as well as technical and scientific support organizations, regulators and educational providers.

This publication captures the current state of knowledge and practices within Member States concerning the development and use of Level 2 Probabilistic Safety Assessments (PSA). It summarizes the key insights shared in discussions during a technical meeting, as well as suggested next steps.

In March 2023, the IAEA organized a Technical Meeting on the Safety Approach for Liquid Metal Cooled Fast Reactors [LMFRs] and the Analysis and Modelling of Severe Accidents. This publication summarizes the material that was presented during this meeting, related to the analysis and modelling of severe LMFR accidents. It covers knowledge on the physical phenomena and the development of models and numerical tools, and their validation through experimental data related to the progression of severe accidents. This publication is intended for public and private sector organizations developing LMFRs, research facilities, organizations responsible for designing LMFRs, operators and contractors, including prospective operators, and regulatory bodies.

This publication provides guidance for developing an effective lessons learned programme to enhance the strategic knowledge management initiatives of nuclear facilities and organizations. Both positive and negative experiences provide opportunities for organizations to learn and improve. These include the experience gained by individuals and teams, through business activities, and from events or incidents (both consequential and non-consequential), as well as industry experience and improvement opportunities derived from external sources. This publication includes case studies from different types of nuclear organizations and supports the development of good practices and successful approaches to lessons learned programmes.

This publication captures recent efforts in the development, improvement, validation, and application of severe accident codes for pressurized heavy water reactors (PHWRs), as well as related research and development. It summarises the information from the IAEA Technical Meeting on PHWR Severe Accident Simulation and Modelling that was held virtually on 20–23 September 2022. The information is detailed in terms of the needs and application of severe accident simulation and modelling, regulatory aspects, updates in experimental programmes and in code development, specifically for PHWRs. The publication is intended for professionals from organizations designing, operating or providing services to PHWRs, regulatory bodies, and other technical support organizations involved in severe accident simulation and modelling of PHWRs.

This TECDOC compiles international experiences and safety practices related to experimental fusion machines. Its objective is to provide an insight into the safety considerations for prototype, demonstration, and future commercial fusion power plants, collectively referred to in this publication as fusion power plants (FPPs). Based on questionnaire responses submitted by experts from various Member States and international organizations, it highlights the safety approaches employed in a range of currently operating and planned experimental fusion facilities, as well as those being developed for future FPPs. The information within this TECDOC aims to improve the general understanding of the safety considerations for future FPPs and will serve as a foundation to determine whether fusion-specific design safety and safety assessment standards may be necessary. This TECDOC is intended for public and private sector organisations with an interest in FPPs, including those involved in research, design, manufacturing, construction, operation, regulation, or technical support. It also targets individual stakeholders engaged in addressing the safety aspects of fusion energy technologies.

Graphite has been used as a moderator and reflector of neutrons in more than 100 nuclear power plants and in many research and plutonium-production reactors, in quantities ranging from a few kilograms to more than 3,000 tonnes, depending on the design. Many of the older reactors have now been shut down, with more approaching the end of their operating lives, and radioactive irradiated graphite have now accumulated worldwide. This publication provides a comprehensive overview of managing irradiated graphite waste provided by the members of The International Project on Irradiated Graphite Processing Approaches (GRAPA) network. This publication is intended for representatives of Member States with a programme involving the management of irradiated graphite, as well as non-governmental or international organizations that represent such programmes regionally or worldwide.

The majority of the hydrogen used presently is produced from fossil fuels, which results in carbon dioxide emissions. Nuclear energy has the potential to replace fossil fuels for supplying a forecasted large increase in the demand of hydrogen with low or zero carbon emissions. There are currently several demonstration projects worldwide ongoing and planned for the production of hydrogen using operational nuclear power plants, as well as developments considering advanced reactor technologies for hydrogen production. The Coordinated Research Project "Assessing Technical and Economic Aspects of Nuclear Hydrogen Production for Near-term Deployment" addressed relevant facets for the potential upscaling of nuclear hydrogen production technologies, based on the specific cases of participant Member States. This publication is intended for scientists and specialists, as well as various stakeholders interested in hydrogen production using nuclear energy.

The objective of this Technical Document is to provide clear guidance including best practices and recommendations for the planning, management and implementation of uranium exploration projects. It provides a systematic approach to the development and implementation of uranium exploration programmes. The intended audience includes, but is not limited to, government decision makers at all levels, governmental officers in mineral resources, government geological surveys, mining operators and individuals, private companies and universities with interests in mineral exploration.