The recommendations provided in this Safety Guide are aimed primarily at operating organizations of nuclear power plants and regulatory bodies. It covers the concept of operational limits and conditions (OLCs), their content as applicable to nuclear power plants, and the responsibilities of the operating organization for their establishment, modification, compliance and documentation. Operating procedures (including emergency operating procedures and severe accident management guidelines) to support the implementation of the OLCs and to ensure their observance are also within the scope of this Safety Guide.
On request, the IAEA performs comprehensive audits of radiotherapy programmes to assess the whole process, including aspects such as organization, infrastructure and clinical and medical physics components. The objective of a comprehensive clinical audit is to review and evaluate the quality of all components of the practice of radiotherapy at the institution, including its professional competence, with a view to quality improvement. A multidisciplinary team, known as Quality Assurance Team in Radiation Oncology (QUATRO), comprising a radiation oncologist. a medical physicist and a radiation therapist, are required to carry out the audit. The present publication provides revisions of the QUATRO guidelines published in 2007, by incorporating new procedures relevant to newer technologies and modalities that have become routinely used in radiotherapy centres in the interim period.
Aimed primarily at regulatory bodies and the operating organizations of nuclear power plants, this Safety Guide provides recommendations on controlling activities relating to modifications to nuclear power plants. It covers modifications relating to plant configuration and to the operating organization, as well as temporary modifications. The responsibilities of the operating organization for the design, safety assessment and review, control, implementation and testing of these modifications are also within the scope of this Safety Guide as are the repair and replacement of equipment and components as part of the maintenance of the plant leading to new components.
Written for use by regulatory bodies and the operating organizations of nuclear power plants, this Safety Guide addresses the commissioning, operation and preparation for decommissioning stages for a nuclear power plant. The role of the operating organization in the siting, design, manufacturing and construction of a nuclear power plant is outside the scope. In most States, the operating organization is the legal entity responsible for safety, financial and commercial obligations, as well as other obligations that are connected with the operation of a nuclear power plant. This Safety Guide is solely concerned with those responsibilities and obligations that are necessary to ensure the safe operation of the nuclear power plant(s) under the control of the operating organization.
The objectives of nuclear criticality safety are to prevent a self-sustained nuclear chain reaction. This Safety Guide provides guidance and recommendations on how to meet the relevant requirements for ensuring subcriticality when dealing with fissile material and for planning the response to criticality accidents. The recommendations address how to ensure subcriticality in systems involving fissile materials during normal operation and during credible abnormal conditions, from initial design through commissioning, operation and decommissioning. This publication also provides recommendations on identification of credible abnormal conditions; performance of criticality safety assessments; verification, benchmarking and validation of calculation methods; safety measures to ensure subcriticality; and management of criticality safety. The guidance and recommendations are applicable to both regulatory bodies and operating organizations.
This Safety Guide is a revision of IAEA Safety Standards Series No. SSG-24, which it supersedes. The current publication provides recommendations on how to meet the applicable safety requirements relating to the utilization and modification of research reactors. The recommendations focus on the categorization, safety assessment and approval of research reactor experiments and modification projects. The publication also incorporates the relevant lessons learned from the accident at the Fukushima Daiichi nuclear power plant and elaborates on interfaces between nuclear safety and nuclear security. Specific safety considerations in different phases of utilization and modification projects are covered, including preimplementation, implementation, and post implementation phases. Guidance is given on operational safety of experiments, including the handling, dismantling, post-irradiation examination and disposal of experimental devices. The publication is intended to be of use to individuals within the operating organizations of research reactors, regulatory bodies, as well as the experimenters, technical support organizations and other persons involved in utilization and modification projects.
Within the overall objective to support the development of fast reactor technology and to extend the predictive capabilities of existing simulation tools for design and safety analysis, this publication aims to improve the understanding of key phenomena involving radioactive material transport and reduce uncertainties in the estimation of potential releases to the environment. It arises from an IAEA coordinated research project (CRP), launched to perform modelling and simulation of the source term for sodium cooled fast reactors under hypothetical severe accident conditions. The publication presents the results and conclusions of the CRP to verify and validate modelling the in-vessel and in-containment source terms. The technical aspects addressed by the CRP are divided into three main parts: the in-vessel source term estimation, the primary system/containment interface source term estimation and the in-containment phenomenology. This publication documents the models, simulations, results and discussions.
Nuclear educational networks have demonstrated their value to support Member States in establishing, running and maintaining nuclear education programmes that are sustainable and aligned with the actual needs and priorities of the sector. Through co-operation among universities, training organizations and industry, national and international networks have enabled the retention, expansion and enhancement of nuclear educational programmes. This publication provides the background, context and drivers for developing and promoting collaboration in nuclear educational, capturing best practices and mechanisms that can aid the establishment and operation of networks. It showcases the experience and achievements of existing networks, providing practical examples of their benefits, outcomes and lessons learned. The publication will be useful to institutions seeking to develop or improve their nuclear education programmes by embarking on collaborative efforts.