This publication presents the outcomes of a collaborative study to analyse the status of nuclear decommissioning activities around the world as of 2020. Future evolution of these activities was also considered. The information presented is based on responses to a questionnaire distributed to organizations with responsibility for planning, implementation and oversight of decommissioning programmes, with baseline information on the numbers and current operational status of nuclear facilities being extracted from the online nuclear facilities databases maintained by IAEA. Analysis of the collected data was undertaken at global and regional levels, rather than at the level of individual States or facility sites. The publication is intended primarily to be of use to individuals with policy responsibilities in the area of decommissioning and associated waste management activities, including government officials, regulators, facility manages and service providers.

The accident at the Fukushima Daiichi Nuclear Power Plant (NPP) led to the radioactive contamination of large areas. The Government of Japan formulated a programme for the recovery of these areas, including remediation efforts. The objective of the recovery strategy, and therefore of the remediation programme, was to improve the living conditions of the people affected by the accident. At the request of the Government of Japan, the IAEA conducted missions to support the remediation of contaminated areas and evaluate progress. These were followed by four bilateral meetings between IAEA and the Japan Ministry of the Environment (MOE). This publication captures the findings and information obtained during the discussions, including on the decontamination process; waste management; monitoring; stakeholder issues; knowledge management; remediation, recovery and regulatory issues. The publication provides consolidated information on the different topics discussed and lessons learned

Nuclear forensics supports national nuclear security measures and criminal investigations by providing information on the identity, origin and history of nuclear or other radioactive material found out of regulatory control. This publication provides information for States on the use of nuclear forensics in response to criminal or other unauthorized acts involving nuclear or other radioactive material, based on the guidance provided in IAEA Nuclear Security Series No. 2-G (Rev. 1), Nuclear Forensics in Support of Investigations. It is intended for technical and non-technical personnel responsible for developing nuclear forensic analytical capabilities within the context of a broader national nuclear forensic programme stemming from national legislation. It provides technical information that describes the application of specific methods, analytical techniques and technical expertise used for nuclear forensic analysis in support of investigations of criminal or other unauthorized acts involving nuclear or other radioactive material.

This Safety Guide, a revision of IAEA Safety Standards Series No. SSG-5, was initiated to provide recommendations on site evaluation, design, construction, commissioning, operation and preparation for decommissioning of conversion facilities and uranium enrichment facilities to meet the applicable requirements established in IAEA Safety Standards No. SSR-4, Safety of Nuclear Fuel Cycle Facilities, which incorporates the lessons learned from the accident at the Fukushima Daiichi nuclear power plant. The revised Safety Guide also reflects current operational practices at conversion facilities and uranium enrichment facilities. The recommendations in this publication are aimed primarily at operating organizations of conversion facilities and uranium enrichment facilities, regulatory bodies and designers.

This Safety Guide provides specific recommendations on the safety of uranium and plutonium mixed oxide (MOX) fuel fabrication facilities. The potential hazards of a MOX fuel fabrication facility are release of actinides, increased radiotoxicity due to trans-uranium actinides, and nuclear criticality. The toxicity of plutonium is high and therefore it is important that best practices be employed at all stages of the fabrication of MOX fuel, and that plutonium be handled, processed, treated and stored safely. The revised Safety Guide reflects current operational practices at MOX fuel fabrication facilities. The recommendations in this publication are aimed primarily at the operating organizations of fuel fabrication facilities, regulatory bodies and designers.

This Safety Guide provides specific recommendations on the safety of uranium fuel fabrication facilities and describes the actions, conditions and procedures for meeting safety requirements. It deals specifically with the handling, processing and storage of low enriched uranium that has a uranium 235 concentration of no more than 6%, derived from natural, highly enriched or reprocessed uranium. This publication is a revision by amendment of IAEA Safety Standards Series No. SSG-6. It addresses the new safety requirements established by IAEA Safety Standards SSR-4, Safety of Nuclear Fuel Cycle Facilities, which incorporates the lessons learned from the accident at the Fukushima Daiichi nuclear power plant.

The operational useful lifetime of semiconductor electronic devices working in harsh radiation environments is limited by the structural defects induced by the exposure to ionizing radiation. This has immediate consequences for their use in high radiation environments, for example in nuclear facilities, satellites, radiotherapy, medical diagnostics, security and other industries. This publication establishes a standardized procedure to quantify the radiation hardness of semiconductor diode materials in a way that is independent of the irradiation parameters and biasing conditions of the device. The established parameter reflects the additional free charge carrier trapping cross section induced by the damaging radiation, normalized to the predicted concentration of generated vacancies by the same radiation. The effectiveness of the approach is validated through different types of ion beam irradiations, characterizations and materials used. The work leads towards approaches to predict the radiation induced effects on device performance for more complex electronic structures.

Accurate measurement of radiation dose received by patients undergoing radiotherapy or medical imaging is essential for ensuring effective and safe healthcare. Equally, accurate measurement of radiation dose is required to guide employers in protecting their workforce from the harmful effects of ionizing radiation. Secondary Standards Dosimetry Laboratories (SSDLs) are specialist laboratories used to provide calibration and guidance for end users in hospitals and industry. This publication provides detailed technical information for countries on how to establish an SSDL, including planning processes, cost estimates and timelines. The technical descriptions and guidelines may also be helpful to existing SSDL radiation metrology staff when upgrading calibration facilities or purchasing new equipment.

This Safety Guide considers the application of a graded approach throughout the lifetime of a research reactor (site evaluation, design, construction, commissioning, operation and preparation for decommissioning), including utilization and experiments that are specific features of research reactor operation. A major aspect of this Safety Guide involves the use of a graded approach in the application of the safety requirements for the design and operation of research reactors, so that the fundamental safety objective to protect people and the environment from harmful effects of ionizing radiation is achieved. It is intended for use by operating organizations, regulatory bodies and other organizations involved in the design, construction and operation of research reactors. This Safety Guide is a revision of IAEA Safety Standards Series No. SSG-22, which it supersedes.

This Safety Report provides practical guidance to governments, regulatory bodies, other relevant competent authorities, and building and construction material industries on setting up arrangements for regulatory control relevant to building and construction materials that give rise to radiation exposures at any step in their life cycle. These steps would include raw material production, manufacturing, supply and end use. It also considers the responsibilities of the suppliers of raw, waste or recycled materials for incorporation into building or construction materials, and it covers verification programmes for building and construction materials prior to their use as well as in completed construction projects.

Medical X-ray equipment technology has evolved exponentially in the last decades, shifting steadily from analogue to digital radiology, from single slice to multidetector-row computed tomography or from fluoroscopy to complex angiography systems. This, however, comes with associated radiation risk for patients and staff. It is therefore vital that all X-ray equipment is monitored in terms of performance to ensure accurate and safe use. Quality control (QC) represents the basic level of managing safety and quality in diagnostic radiology. This publication compiles all existing QC tests in literature for all X-ray modalities. To facilitate the use of this handbook, spreadsheets and video tutorials have been developed to help with the execution of tests.