This publication, which draws upon the outcome of an IAEA coordinated research project, presents methodologies for assessing pipe failure rates in advanced water cooled reactors (WCRs), including a comprehensive review of good practices for the assessment of piping reliability parameters for advanced WCRs. Good practices are those processes and analytical tasks that would be expected in piping reliability analysis in order for the results to be realistic representations of piping structural integrity. This publication builds on technical insights that have been obtained using different methodologies when applied in multiple analytical contexts and responding to the requirements of different national codes and standards. It provides Member States with a strong technical basis for establishing design and plant centric piping reliability parameters for input into probabilistic safety assessment studies, in-service inspection programme development, and operational support. Additionally, an objective evaluation and inter-comparison of methods used in participating Member States is outlined leading to a harmonization of the practices relevant to newly deployable advanced WCRs.

Boron neutron capture therapy (BNCT) is a neutron-based technique that allows selective cancer treatment at the tumour cellular level. BNCT is especially suitable for the treatment of brain, head, neck and skin cancers. Using the reaction between a neutron and boron to selectively destroy cancer cells, BNCT is a treatment that differs radically from conventional radiotherapy and promises to become a more widely adopted option for cancer treatment. BNCT is undergoing a major resurgence of interest around the world as some recent progress in accelerator technology allows the procedure to be undertake in clinics. In addition, the approval of BNCT in Japan as a routine clinical treatment for certain tumour types offers valuable insights for other states considering a similar approach. This publication comprehensively reports on the current state of the science as well as the supporting technology. It covers accelerator-based neutron sources, beam design, physical dosimetry, facility design and operation, pharmaceuticals, radiobiology, dose calculation, treatment planning and clinical trials. It has been written to assist in decision making at the national level as well as offering practical guidance for all those involved in implementation and ongoing management of BNCT programmes.

The transport of radioactive material is an essential activity worldwide. To ensure the protection and safety of people, property and the environment, appropriate regulations for the safe transport of radioactive material, both at the national level and at the international level, are necessary. Competent authorities regulate the transport of radioactive material through the application of national regulations, which should be consistent with relevant international regulations. This Safety Guide provides recommendations on actions that competent authorities should take to ensure compliance with the applicable regulations for the safe transport of radioactive material.

This Safety Guide provides recommendations on the operating organization and on personnel for research reactors to meet the relevant requirements of IAEA Safety Standards Series No. SSR-3, Safety of Research Reactors. It covers the typical operating organization for research reactor facilities; the recruitment process and qualification in terms of education, training and experience; programmes for initial and continuing training; the authorization process for those individuals having an immediate bearing on safety; and the processes for their requalification and reauthorization. This Safety Guide is a revision of IAEA Safety Standards Series No. NS-G-4.5, which it supersedes

The ageing of structures, systems and components is one of the major challenges faced by nuclear fuel cycle facilities worldwide. This publication is intended to provide information on methods, approaches, practices and strategies for ageing management of nuclear fuel cycle facilities. It provides practical information on the establishment of effective ageing management programmes for nuclear fuel cycle facilities in the operational stage and on ageing management considerations in different stages in the lifetime of a nuclear fuel cycle facility. It also addresses the interface of ageing management with other technical areas and programmes, including maintenance, periodic testing and inspection, equipment qualification and configuration management. Best practice examples on how Member States are addressing ageing issues in nuclear fuel cycle facilities are also provided in this publication.

This publication aims to outline credible technical options for managing separated plutonium. There is no attempt to rank or rate any of the options, instead the intent is to inform the reader of the technical merits of the various options and the state of their development. It is primarily focused on Member States that have adopted a closed fuel cycle policy but can also be of value to other Member States, specifically their decision makers and other stakeholders involved in potential future nuclear fuel cycles, by informing them on life cycle options and energy policy.

Sites with radioactive contamination may require action to protect people and the environment and to enable transition to a different future use. To support environmental management of these sites, this publication presents a process to determine the “end state” of the site to be remediated or being remediated, and implications for the site future use and necessary controls. The approach is intended to assist those responsible for a site in making an informed and transparent decision on what is the mutually agreed end state. It provides a common basis for all stakeholders involved in the decision-making process, who are working on achieving consensus, so that the potential for misunderstanding is reduced.

Probabilistic methods are increasingly being used to complement deterministic methods in assessing the safety and ensuring the reliability of research reactors. Addressing features specific to research reactors, this publication suggests a practical approach for the development and implementation of a project using probabilistic methods in terms of objective, scope, data and modelling, as well as the application of results to enhance safety and reliability. This publication is intended to be used by operating organizations, regulatory bodies and technical support organizations when performing or reviewing research reactor assessments in which probabilistic methods are applied. It will ideally be read in conjunction with relevant IAEA Safety Standards Series publications and technical guidelines for safety analysis, operation and maintenance, and component reliability data for research reactors.