IAEA Member States have expressed relevant interest in the development and deployment of small and medium-sized or modular reactors (SMRs) to help cover their energy needs in the coming decades. SMR designs may include technological characteristics that differ significantly from those of the large nuclear power plants that are commercially available. Those SMR characteristics can represent a challenge when the existing design requirements, as established in IAEA Safety Standards Series No. SSR-2/1 (Rev. 1) Safety of Nuclear Power Plants: Design, are intended to be applied to SMRs. This publication focuses on the engineering judgement necessary to apply each of the design requirements in SSR-2/1 (Rev. 1), and also the entire set of requirements, to light water cooled and high temperature gas cooled SMRs. The publication includes the common ground reached by representatives from regulatory bodies, technical and scientific support organizations (TSOs) and SMR design organizations regarding the applicability of the design requirements to both SMR technologies. The insights provided are also intended to contribute to motivating further progress in the harmonization of national and international views on safety approaches for SMR technologies. This publication is intended for use by organizations dealing with nuclear power plant design or operation, and by regulatory bodies and TSOs, particularly from countries that are initiating or enlarging nuclear power programmes that include SMR units.

Spent nuclear fuel which is generated in the operation of nuclear reactors needs to be safely managed following its removal from the reactor core. On-site power reactor storage pools were designed on the assumption that after a short period of time spent nuclear fuel would be removed for reprocessing and disposal or further storage elsewhere. The amount of highly radioactive spent fuel that needs to be stored over longer periods of time is growing and additional storage capacity is required. One of the widely used options for additional storage capacity is the use of casks for dry storage of spent fuel. Among various existing dry storage concepts, several Member States are utilizing a concept of dual purpose casks (DPCs). This publication provides practical advice on the structure and contents of a DPC integrated safety case with reference to existing IAEA requirements relevant to the licensing and use of transport and storage casks for spent fuel.

Probabilistic safety assessment (PSA) is considered to be an important tool for assessing the safety of nuclear installations (typically used for safety assessment of nuclear power plants) in relation to potential initiating events that can be caused by random component failure and human error, as well as internal and external hazards. The purpose of seismic PSAs performed on nuclear installations is to provide risk insights related to their seismic robustness. The methodology for seismic safety evaluations includes a combination of deterministic and probabilistic approaches. Their applications typically address the impact of beyond design basis seismic events. This publication provides a detailed methodology for seismic PSA in line with the current international practices for seismic safety assessment of nuclear installations. Taking into account recommendations provided in IAEA safety standards and information reflected in internationally recognized technical standards, it reflects the current state of practice in the area of seismic PSA.

Industrial computed tomography for advanced industrial non-destructive evaluation is a complex technological area, encompassing nuclear radiation detectors, mechanical engineering, computational mathematics and radiation physics. Additionally, the cost of applying this technology may be prohibitive. This guidebook provides an introduction to gamma computed tomography for non-destructive evaluation imaging in the simplest configuration. It is intended to be of use to the non-destructive testing community, currently practicing conventional radiography techniques. It provides clear information on the relevant practical issues and problems related to setting up computed tomography for industrial non-destructive testing and establishes a basis for understanding the intricacies of the technology.

The design and operational requirements of nuclear facilities, such as nuclear power plants (NPPs), are specified and managed to ensure the safety and optimized operation of the facility. These requirements and how they are managed, interpreted and used to support facility functions and activities, are very important in all the life cycle phases of the facility from design through construction, commissioning, operation, and from refurbishment to decommissioning. This publication analyses and provides new insights into the different approaches followed by the nuclear industry for their effective management as well as guidance to develop a comprehensive requirement management programme in nuclear facilities. Although the guidance provided is based on industry experience to develop such programmes for NPPs, the principles and approaches provided can be used in all nuclear facilities including research reactors, fuel manufacturing facilities, fuel reprocessing and waste management facilities.

This publication explores disposal concepts that can be applicable for Member States with small inventories of intermediate and high level waste. The concepts are evaluated for their potential suitability in a number of situations. Case studies are included, some of which look at facilities that are being planned or operated. Others, such as disposal in deep boreholes, have only been examined at a conceptual level.

Fuel acceptance criteria can be used, among other things, as key inputs in the determination of operating limits and conditions for reactor operational states, in the determination of fitness for service criteria for anticipated operational occurrences, in the formulation of special safety system trip set points for accident conditions, and in the determination of a plant's safe operating envelope. This publication presents a collection of current practices of fuel acceptance criteria used in States with operating pressurized heavy water reactors (PHWRs) and provides the technical justification available for such criteria conditions. Following a technical meeting and a survey conducted on the use of fuel acceptance criteria in all PHWR operating States, this publication provides an overview of the role PHWR fuel acceptance criteria play in nuclear safety and details the technical basis of the reported fuel acceptance criteria. Topics where collaboration and further discussion between participating States would be beneficial are also highlighted.

The Fuel Incident Notification and Analysis System (FINAS) is jointly operated by the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organization for Economic Co-operation and Development (OECD/NEA). The system is an important tool for international exchange of operating experience from nuclear fuel cycle facilities. FINAS reports contain information about events of safety significance that have occurred at nuclear fuel cycle facilities and describe the root causes and lessons learned from the events. This publication provides a summary of the operating experience feedback from the events reported to FINAS since it was launched in 1992. The publication has a focus on the root causes, lessons identified, and corrective actions taken to prevent the occurrence of similar events. Reference to other publications that cover nuclear fuel cycle facilities’ events as well as a description of the operating experience programmes of these facilities is included. The publication is intended to be used by nuclear fuel cycle facilities’ operators, regulators, and designers.

New geochemical and mineralogical data from research conducted under the IAEA coordinated research project entitled Geochemical and Mineralogical Characterization of Uranium and Thorium Deposits has resulted in a better understanding of the genesis of uranium and thorium mineralization. This publication presents a summary of the research and selected papers from the project’s partners. The results are expected to enhance exploration programmes, resource evaluation and sustainable supply of uranium and thorium for peaceful purposes.

The publication focuses on radioecologjcal experience and data acquired and lessons learned in Japan following the nuclear accident at the Fukushima Daiichi nuclear power plant in March 2011. The publication brings together outcomes of the extensive studies, done by Japanese scientists and their colleagues from other countries, on characterization of radioecological transfer parameters in the terrestrial and aquatic environments of Japan affected by radionuclides released in the accident. The Japan specific data are systematically presented and compared to the global experience gained from the earlier nuclear accidents, military or industrial activities. Climate, landscape, agriculture and food processing practices, lifestyle and national dietary customs are shown as factors influencing transfer of radionuclides through the environment and human food chains. The publication summarizes country specific experience and puts it into existing global radioecological contexts.

The IAEA reports on lessons learned and actions taken after the Fukushima Daiichi Accident. This publication addresses the challenges faced and the ongoing needs of Member State organizations which have been implementing and maintaining post-Fukushima actions. It discusses the actions taken (or to be taken), good practices and describes effective solutions to issues in implementation, verification, qualification and maintenance. Also discussed are the approaches to measuring and maintaining effectiveness of actions as well as an analysis of merits, costs and benefits. Examples in decision making for implementation and follow-up policies, programmes and procedures to ensure sustainability in the long term are presented.

In industrial processes, it is useful to have a range of non-intrusive techniques that can effectively 'look' through vessel and pipe walls to measure process parameters and to identify plant problems. Sealed radioactive sources, specifically those that emit gamma radiation and neutron particles, are ideally suited for these purposes and have been used for industrial applications for many years. This publication describes several available techniques with sealed radioactive sources, by showing examples of their use in industrial applications and by demonstrating how they can be used to improve process efficiency and to save money. The focus of the publication corresponds to two major techniques with sealed radioactive sources: gamma scanning and neutron backscattering, which are largely applied for diagnosis and troubleshooting in processing vessels, columns and in pipes.