Distribution Coefficients for Soil, Freshwater and Marine Systems for Exposure AssessmentsIAEA TECDOC Series No. 2095 This publication was developed as part of the IAEA’s MODARIA I and MODARIA II programmes, which focus on modelling and data for radiological impact assessments. It presents the outcomes of Working Group 4, which considered the update and improvement of distribution coefficient (Kd) values used in environmental models for exposure assessment for soil, freshwater, and marine systems. As part of this effort, Kd datasets for soils and freshwater sediments were compiled. These datasets include associated chemical, physical, mineralogical, and other ancillary properties, along with detailed methodological guidance to support end users in selecting appropriate Kd values for their specific applications. For marine sediments, Kd data were compiled using sources from Japan, the Baltic Sea, and the IAEA’s Marine Radioactivity Information System (MARIS) database. These values were then compared with those published in the IAEA Technical Reports Series No. 422, Sediment Distribution Coefficients and Concentration Factors for Biota in the Marine Environment. This publication is intended for environmental regulators, scientists, modellers and assessors. |
Safety of Nuclear Fuel Reprocessing FacilitiesIAEA Safety Standards Series No. SSG-42 (Rev. 1) This Safety Guide provides recommendations on safety in the siting, design, construction, commissioning, operation and preparation for the decommissioning of nuclear fuel reprocessing facilities to meet the relevant requirements established in the IAEA Safety Standards Series No. SSR-4, Safety of Nuclear Fuel Cycle Facilities. It provides specific recommendations on the safety of nuclear fuel reprocessing facilities that use the PUREX process to reprocess fuels containing uranium and plutonium. It does not specifically address the reprocessing of thorium from fast breeder reactors or other advanced reactor systems, or the partitioning of radionuclides other than uranium and plutonium. However, the similarity between aqueous processes allows for the application of most of the recommendations provided in this Safety Guide, with suitable adjustments to facilities reprocessing other types of nuclear fuel. This publication is intended for operating organizations and designers of nuclear fuel reprocessing facilities and relevant technical support organizations and regulatory bodies. |
Safety of Nuclear Fuel Cycle Research and Development FacilitiesIAEA Safety Standards Series No. SSG-43 (Rev. 1) This Safety Guide provides recommendations on safety in the siting, design, construction, commissioning, operation and preparation for the decommissioning of nuclear fuel research and development facilities to meet the relevant requirements established in IAEA Safety Standards Series No. SSR-4, Safety of Nuclear Fuel Cycle Facilities. It applies to all types of nuclear fuel cycle research and development facility, including facilities involving small scale experiments, analyses and fundamental research studies on the chemical, physical, mechanical and radiological properties of specific materials such as prototype nuclear fuels (before and after reactor irradiation) and investigations of nuclear materials and wastes arising from new processes, and facilities involving research and development on processes and equipment envisaged for use on an industrial scale (e.g. pilot facilities for waste treatment). This publication is intended for operating organizations and designers of nuclear fuel cycle research and development facilities and relevant technical support organizations and regulatory bodies. |
Guidelines for the Harmonization of Education and Training Requirements in RadiopharmacyTraining Course Series No. 88 IAEA-TCS-88, 44 pp.; 1 figures; 2025, English. Date of Issue: 7/2/2025. |
Development and Application of Level 2 Probabilistic Safety Assessment for Nuclear Power PlantsIAEA Safety Standards Series No. SSG-4 (Rev. 1) Probabilistic safety assessments (PSAs) are recognized as an important tool for assessing the level of safety for nuclear power plants (NPPs). In particular, the Level 2 PSA for NPPs provides key insights about the potential radioactive releases that could affect the workers, the public and the environment following a severe accident. The purpose of this Specific Safety Guide is to provide an updated internationally accepted methodology for the development of a high-quality Level 2 PSA for NPPs. The revised Specific Safety Guide is intended for use by designers, operating organizations, technical support organizations and regulatory bodies in the development, application and independent review of Level 2 PSAs. The revised Safety Guide is also intended for use in connection with both the review for authorization (licensing) of the construction and the operation of new NPPs and the safety re-evaluation of existing NPPs during periodic safety reviews and modifications. |
Nuclear Decommissioning: Addressing the Past and Ensuring the FutureProceedings Series This proceedings publication comprises key outcomes and proposed recommendations from the conference held to discuss the achievements, challenges, and lessons learned in the decommissioning of nuclear facilities. Important information was shared at the conference on current priority needs, strategies and approaches to support the safe, secure, and cost-effective implementation of decommissioning programmes. In addition, this publication features the President’s and Vice-President’s reports, with insights drawn from speaker presentations, panel discussions, side events and Q&A sessions with contributions from participants. |
Development and Application of Level 1 Probabilistic Safety Assessment for Nuclear Power PlantsSeriya norm MAGATE po bezopasnosti No. SSG-3 (Rev. 1) STI/PUB/2056, 295 pp.; 9 figures; 2025 |
Experience in the Management of Radioactive Waste After Nuclear Accidents: A Basis for PreplanningIAEA Nuclear Energy Series (Russian) NW-T-1.31 STI/PUB/2022, 211 pp.; 64 figures; 2025 |
Good Practices in the Maintenance of Operating Nuclear Power PlantsIAEA TECDOC Series No. 2094 Maintenance is a core activity that ensures the safe, reliable, and cost-effective operation of nuclear power plants throughout their expected lifetimes. This publication collates knowledge and insights from experts from various Member States and identifies general good practices — rather than specific examples — that maintenance managers and personnel can adopt to promote consistently high performance in maintenance. It provides guidance to help navigate some common challenges, such as retaining a highly skilled and committed workforce, optimizing maintenance programmes and efficiently overseeing suppliers and additional staff. It also examines the fundamental aspects of maintenance, such as managerial approach to conducting maintenance activities; the planning and control of maintenance activities with a focus on contractor oversight; the management of documentation and personnel skills; the use of key performance indicators; and the conduct of benchmarks. |
Non-ergodic Ground Motion Models for Site Specific Seismic Hazard Assessment at Nuclear Installation SitesIAEA TECDOC Series No. 2093 The Regional Cooperative Agreement for Research, Development, and Training Related to Nuclear Science and Technology for Asia and the Pacific (RCA) was established in 1972 and has since benefited from the IAEA Technical Cooperation (TC) programme. Highlighting the socio-economic impact of the RCA in the region is crucial. Therefore, National RCA Representatives have endorsed an initiative to conduct a social and economic impact assessment of the RCA programme supported under the IAEA TC programme from 2000 to 2023. The results of these assessments will be published and disseminated to RCA State Parties, relevant stakeholders, and the public. This report is one of the planned four reports in the areas of air quality monitoring, food safety, groundwater and nuclear medicine. |
Education and Training Appraisal in Radiation Protection and Safety (EduTA) IAEA Services Series No. 51 IAEA-SVS-51, 35 pp.; 1 figures; 2025, English. 0.00 Euro. Date of Issue: 5/29/2025. |
Security of Nuclear and Other Radioactive Material in TransportCollection Sécurité nucléaire de l’AIEA Nº 46-T STI/PUB/2090, 71 pp.; 1 figures; 2025 |
The BIOMASS MethodologySafety Reports Series No. 126 This publication describes the work undertaken by Working Group 6: Biosphere Modelling for Long Term Safety Assessments of Waste Disposal Facilities of the IAEA’s Modelling and Data for Radiological Impact Assessments (MODARIA II) programme (2016–2019). The objective of this publication is to provide updated guidance for addressing the biosphere in undertaking post-closure safety assessments for solid radioactive waste disposal, building on the original BIOMASS methodology published in 2003. The intended audience includes regulators and organizations responsible for assessing and reviewing safety assessments and assessors and modellers involved in a range of radiological studies within the nuclear industry. |
Social and Economic Impact Assessment of Air Quality Monitoring Projects under the RCAThis report evaluates the social and economic impacts of air quality monitoring programmes implemented from 2020 to 2024, supported by the IAEA under the Regional Cooperative Agreement for Research, Development and Training related to Nuclear Science and Technology for Asia and the Pacific (RCA). It is one of four thematic assessments examining the application of nuclear science and technology in air quality monitoring, food safety, isotope hydrology and nuclear medicine. Focusing on air quality monitoring, this publication draws on robust evidence from 19 participating State Parties, IAEA administrative data, expert insights, four success stories and a cost-benefit analysis of air quality monitoring initiatives. It highlights how technical cooperation projects leveraging nuclear science and technology on benefits of air quality monitoring have contributed meaningfully to sustainable social and economic development across Asia and the Pacific. This publication not only highlights tangible outcomes but also emphasizes the collective value created beyond what countries could achieve alone. It is a compelling demonstration of science in action—supporting cleaner air, stronger collaboration and lasting regional progress. IAEA/PAT/010, 124 pp.; 36 figures; 2025, English. 0.00 Euro. Date of Issue: 5/14/2025.  Full Text, (File Size: 10 KB). |
Coated Particle Fuels for High Temperature Gas Cooled Small Modular ReactorsIAEA TECDOC Series No. 2090 This publication contains the latest information on coated particle fuel technologies and may be used as a baseline reference to support the fuel technologies of high temperature gas-cooled reactor (HTGR) small modular reactors (SMRs). The HTGR concept is considered a promising nuclear reactor technology due to its inherent safety and operational features. A typical example of its unique core design is the inert, single-phase coolant (helium gas) coupled with a high-temperature, high-heat capacity moderator (graphite), which allows for a greater response time to core heat up accidents. As HTGRs have the potential to supply high temperature process heat, many other applications such as hydrogen production and electricity generation are also viable. Coated particle fuel technology research programmes have been pursued in several Member States, including the design, manufacturing, characterization, irradiation behaviour and behaviour prediction, accident tests and simulations. This TECDOC is a resource for researchers and for nuclear power plant engineers and operators, fuel technology engineers and designers, and material science engineers. |