This publication summarizes the results of an IAEA technical meeting to review and discuss the analysis, simulation, and modelling of severe accident progression in spent fuel pools. The emphasis was on achieving a better understanding of drivers for improvement to address risks associated with accidents in spent fuel pools, progression to failure of the spent fuel, and the subsequent release of fission products. Discussion sessions enabled the exchange of information regarding the analysis of severe accidents in spent fuel pools, the provision of an overview of current research and development (R&D) activities, and considerations for the planning and execution of further R&D. The meeting served as a forum for Member States to exchange knowledge on current and new code development and methodologies, to identify the gaps for future improvements, and gather information for collaboration on all these aspects.
Since their clinical use initiation in the 1970’s, Fluorine-18 (F-18) radiopharmaceuticals continue to play an important role in nuclear medicine. It is therefore essential to make available broad information on practical production routes and optimal quality control for F- 18 tracers, to achieve the best possible products in high quantity and quality for clinical applications while fulfilling all regulatory requirements. This publication describes the chemical and biological properties of F-18 radiopharmaceuticals. This includes aspects relating to F-18 target production and radiofluorination methods, with focus on the applied techniques. The publication presents a disease oriented approach, describing F-18 radiopharmaceuticals, ranging from the physiological/biological aspects to dedicated radiopharmaceutical development approaches and provides readers with clear guidelines and methods for the production of F-18 radiopharmaceuticals.
This publication presents the outcomes of an IAEA coordinated research project on assessing the national economic effects of nuclear programmes in participating Member States. It provides a short description of the extended input–output model for sustainable power generation (EMPOWER), developed by the IAEA, and presents concise summaries of its applications. It further includes the results produced by the contributing research teams and summarizes general insights drawn from the national studies. The publication illustrates the state of the art of assessing macroeconomic impacts of nuclear energy programmes. It is expected to support further applications of advanced models to improve the understanding of macroeconomic and sectoral impacts of building and operating nuclear power plants
Neutron beam techniques, such as neutron scattering, have a widespread use. An overview of up-to-date technical information on neutron scattering techniques and on instrumentation for neutron scattering is presented in this publication, which draws upon the outcome of an IAEA technical meeting. It presents the main applications utilizing low and medium flux neutron sources, that could be the object of research and development or are relevant in education and training. It is intended to support research reactor and accelerator facilities in developing their neutron scattering techniques and expanding their neutron scattering capabilities.
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.
An example of a limited scope INPRO sustainability assessment of an innovative nuclear energy system used the BN-1200 fast reactor as a case study. The INPRO assessment was performed at the full-depth criteria level and helped to identify actions for sustainable long term deployment of sodium cooled fast reactors. The publication describes the application of the INPRO sustainability assessment method to the innovative nuclear energy system based on BN-1200 fast reactors in the areas of economics and safety of nuclear reactors. The case study is intended to verify readiness of the updated INPRO Methodology for assessment of the sodium cooled fast reactors and to develop recommendations for further improvements to the INPRO assessment method.
As part of the IAEA programme on International Generic Ageing Lessons Learned (IGALL), this publication provides a summarized description of internationally accepted practices. Examples of the national approaches to ageing management for the specific periods of extended shutdown, delayed construction and post final shutdown as applied in the nuclear power plants of participating IGALL Member States are presented. In addition, some of the information is also applicable for the evaluation of ageing effects prior to and after restarting operation. The publication complements existing IAEA publications on ageing management approaches of Member States during normal operation and is intended for use by regulatory bodies, operating organizations, manufacturers, designers and technical support organizations.
This publication summarizes experience and data relevant to the production of 43/44Sc, 61Cu and 86Y as theranostic pairs to the therapeutic nuclides 47Sc, 67Cu and 90Y. Demand for these radioisotopes is expected to grow in coming years. The publication is meant to give the reader hands on information to select the appropriate nuclide to be used in the imaging application of a theranostic pair. It discusses the different production routes and outlines advantages and disadvantages of direct production versus generator production in some cases. It lists different purification techniques including recovery of the starting material where necessary, and details quality control approaches for the different options.The overall aim is to enable readers involved in radiopharmaceutical production and/or quality control to apply these production approaches in their facilities as part of their respective programmes.
This publication presents practical information on occupational radiation protection and examples with good practices from the nuclear industry on how to comply with the requirements established in IAEA Safety Standards Series No. GSR Part 3, Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards, within the context of decommissioning activities. This publication can be used in the planning of new decommissioning projects and for improvements in the implementation of existing decommissioning projects. Useful input for licensing and supervision of decommissioning projects are also provided.
This publication presents a review of technical solutions providing both corrective actions and preventive measures to reduce the ingress of radon indoors. A description of methods, design and implementation of measures to reduce ingress of radon into buildings, and of the materials and equipment used in these solutions are included. The publication also presents methods for measuring gamma radiation from radionuclides in building and construction materials and for methods of reducing exposure due to this gamma radiation. Aimed primarily at building and construction professionals designing and installing radon preventive and mitigation measures, this publication will also be a useful resource for national authorities responsible for the development of national building codes and implementation of national radon action plans.
Typically, discussions of the uranium production cycle are focused on either the economic extraction of resources, or on the environmental and remediation aspects as parallel aspects in a linear cradle-to-grave process. In this publication, resource evaluation is expanded to the full life of the mine to include evaluation of resources in residual waste products. This is viewed in the context of potential reuse or remining of so-called anthropogenic resources in a circular economy. The publication is intended to not only provide a preliminary inventory of uranium contained in mine wastes including the desirable goal of comprehensive extraction in the (uranium) mining industry, but also to provide an initial framework to integrate this aim with those of environmental and remediation considerations in achieving zero waste.
This publication was produced as part of the Working Group 4 of the IAEA Modelling and Data for Radiological Impact Assessments (MODARIA) programme, which focused on the analysis of radioecological data in IAEA Technical Reports Series publications to identify key radionuclides and associated parameter values for human and wildlife exposure assessment. The intent is to reduce uncertainties and to develop new approaches to strengthen the evaluation of the radiological impact to the public, as well as to flora and fauna, arising from radionuclides in the environment. The publication comprises two main sections. The first one considers prioritization approaches to identify the radionuclides and pathways that potentially contribute most to internal and external exposure to organisms in wildlife groups for different sources and exposure situations. The focus of the second section is the improvement of transfer parameter values for animal product data, namely cow and goat milk. Milk was selected as it often has a high priority in radiological environmental impact assessment. Examples of approaches that can be used to identify potentially important data gaps, illustrated using case studies are also presented. This publication is intended to provide Member States with technical information and data that can be used by their national authorities to develop and improve their models and approaches for radiological environmental impact assessment for facilities and activities.