These are e-versions of the IAEA Safety Standards and​ Nuclear Security Series publications​, displayed in the hierarchical order. You can scroll or search by a publication number or a key word or phrase to find the publication​ you are interested in.​ By clicking on a title or the arrows after this title you will open a box showing a short description of that document. ​

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Safety Fundamentals Safety Requirements Safety Guide Nuclear Safety Glossary Report Nuclear Security Fundamentals Nuclear Security Recommendations Nuclear Security Implementing Guide Nuclear Security Technical Guidance Nuclear Security Glossary DPP

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Fundamental Safety Principles, SF-1 (2006). This publication states the fundamental safety objective and ten associated safety principles, and briefly describes their intent and purpose. The fundamental safety objective applies to all circumstances that give rise to radiation risks. The safety principles are applicable, as relevant, throughout the entire lifetime of all facilities and activities — existing and new — utilized for peaceful purposes, and to protective actions to reduce existing radiation risks. They provide the basis for requirements and measures for the protection of people and the environment against radiation risks and for the safety of facilities and activities that give rise to radiation risks, including, in particular, nuclear installations and uses of radiation and radioactive sources, the transport of radioactive material and the management of radioactive waste.
The objective of this Safety Requirements publication is to establish requirements in respect of the governmental, legal and regulatory framework for safety. The framework for safety is to be established for the entire range of facilities and activities, from the use of a limited number of asfd radiation sources to a nuclear power programmes. This Safety Requirements publication covers the essential aspects of the governmental and legal framework for establishing a regulatory body and for taking other actions necessary to ensure the effective regulatory control of facilities and activities — existing and new — utilized for peaceful purposes. Other responsibilities and functions are also covered, such as liaison within the global safety regime and liaison for providing the necessary support services for the purposes of safety (including radiation protection), emergency preparedness and response, nuclear security, and the State system of accounting for, and control of, nuclear material....
The objective of this Safety Requirements publication is to establish requirements that support Principle 3 of Fundamental Safety Principles, in relation to establishing, sustaining and continuously improving leadership and management for safety, and an effective management system. This is essential in order to foster and sustain a strong safety culture in an organization. Another objective is to establish requirements that apply Principle 8, which states that “All practical efforts must be made to prevent and mitigate nuclear or radiation accidents."
These Standards establish requirements for the protection of people and the environment from harmful effects of ionizing radiation and for the safety of radiation sources. These Standards apply for protection against ionizing radiation only, which includes gamma rays, X rays and particles such as beta particles, neutrons, protons, alpha particles and heavier ions. While these Standards do not specifically address the control of non-radiological aspects of health, safety and the environment, these aspects also need to be considered. Protection from harmful effects of non-ionizing radiation is outside the scope of these Standards.
The objective of this Safety Requirements publication is to establish the generally applicable requirements to be fulfilled in safety assessment for facilities and activities, with special attention paid to defence in depth, quantitative analyses and the applications of a graded approach to the ranges of facilities and of activities that are addressed. The publication also addresses the independent verification of the safety assessment that needs to be carried out by the originators and users of the safety assessment. This publication is intended to provide a consistent and coherent basis for safety assessment across all facilities and activities, which will facilitate the transfer of good practices between organizations conducting safety assessments and will assist in enhancing the confidence of all interested parties that an adequate level of safety has been achieved for facilities and activities.
The objective of this Safety Requirements publication is to establish, on the basis of the principles established in the IAEA Safety Fundamentals SF-1, the requirements that must be satisfied in the predisposal management of radioactive waste. This publication sets out the objectives, criteria and requirements for the protection of human health and the environment that apply to the siting, design, construction, commissioning, operation and shutdown of facilities for the predisposal management of radioactive waste, and the requirements that must be met to ensure the safety of such facilities and activities.
General Safety Requirements Part 6 on Decommissioning of Facilities The objective of this publication is to establish the general safety requirements to be met during planning for decommissioning, during conduct of decommissioning actions and during termination of the authorization for decommissioning.
The present publication establishes the requirements for an adequate level of preparedness and response for a nuclear or radiological emergency. The application of these requirements is also intended to mitigate the consequences of a nuclear or radiological emergency if such an emergency arises despite all efforts made to prevent it. The fulfilment of these requirements will contribute to the harmonization worldwide of arrangements for preparedness and response for a nuclear or radiological emergency. These requirements are intended to be applied by the government at the national level by means of adopting legislation and establishing regulations, and by making other arrangements, including assigning responsibilities (e.g. to the operating organization or the operating personnel of a facility or an activity, local or national officials, response organizations or the regulatory body) and verifying their effective fulfilment. The requirements are also intended for use by response...
This publication establishes requirements and provides criteria for ensuring safety in site evaluation for nuclear installations. The Safety Guides on site evaluation listed in the references section provide recommendations on how to meet the requirements established in this publication. A review of Safety Requirements publications was commenced in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan. The review revealed no significant areas of weakness and resulted in just a small set of amendments to strengthen the requirements and facilitate their implementation, which are contained in the present publication.
This publication establishes design requirements for the structures, systems and components of a nuclear power plant, as well as for procedures and organizational processes important to safety that are required to be met for safe operation and for preventing events that could compromise safety, or for mitigating the consequences of such events, were they to occur. This publication is intended for use by organizations involved in design, manufacture, construction, modification, maintenance, operation and decommissioning for nuclear power plants, in analysis, verification and review and in the provision of technical support, as well as by regulatory bodies.
The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the safety objective and safety principles that are established in the Fundamental Safety Principles. This publication deals with the safe commissioning and operation of a nuclear power plant. It covers commissioning and operation up to the removal of nuclear fuel from the plant, including maintenance and modifications made throughout the lifetime of the plant. It covers the preparation for decommissioning but not the decommissioning phase itself. The publication also establishes additional requirements relating only to commissioning. Normal operation and anticipated operational occurrences as well as accident conditions are taken into account.
This Safety Requirements publication establishes requirements for all main areas of safety for research reactors, with particular emphasis on requirements for design and operation. It explains the safety objectives and concepts that form the basis for safety and safety assessment for all stages in the lifetime of a research reactor. Technical and administrative requirements for the safety of new research reactors are established in accordance with these objectives and concepts, and they are to be applied to the extent practicable for existing research reactors. The safety requirements established in this publication for the management of safety and regulatory supervision apply to site evaluation, design, manufacturing, construction, commissioning, operation (including utilization and modification), and planning for decommissioning of research reactors (including critical assemblies and subcritical assemblies). The publication is intended for use by regulatory bodies and other...
The objective of this publication is to establish requirements that, in the light of experience and the present state of technology, must be satisfied to ensure safety, for all stages in the lifetime of a nuclear fuel cycle facility, i.e. its siting, design, construction, commissioning, operation and decommissioning. It is intended to be used by designers, operating organizations and regulators for ensuring the safety of fuel cycle facilities.
The objective of this Safety Requirements publication is to set out the safety objective and criteria for the disposal of all types of radioactive waste and to establish, on the basis of the principles established in SF-1 (2006), the requirements that must be satisfied in the disposal of radioactive waste. This Safety Requirements publication is intended for use by all persons responsible for, and concerned with, radioactive waste management and making decisions in relation to the development, operation and closure of disposal facilities, especially those persons concerned with the related regulatory aspects.
The objective of these Regulations is to establish requirements that must be satisfied to ensure safety and to protect persons, property and the environment from the effects of radiation in the transport of radioactive material. This protection is achieved by requiring (a) Containment of the radioactive contents; (b) Control of external radiation levels; (c) Prevention of criticality; (d) Prevention of damage caused by heat.
The primary objectives of this Safety Guide are: —To provide guidance on those selected elements of the Requirements GS-R-2 (now superseded by GSR Part 7) for which guidance has been requested by Member States and for which there is an international consensus on the means to meet these requirements; —To describe appropriate responses to a range of emergencies; —To provide background information, where appropriate, on the past experience that provided a basis for the Requirements, thus helping the user to better implement arrangements that address the underlying issues.
The objective of this publication is to provide generic guidance for establishing, implementing, assessing and continually improving a management system that integrates safety, health, environmental, security, quality and economic elements, in order to meet the requirements established in GS-R-3 (now superseded by GSR Part 2). This Safety Guide also provides illustrative examples of the application of the management system requirements.
The objective of this publication is to provide recommendations and guidance supplementary to those provided in GS-G-3.1 on Application of the Management System for Facilities and Activities for establishing, implementing, assessing and continually improving a management system that integrates elements of safety, health, environment, security, quality and economics. All the topics covered correspond to requirements established in GS-R-3 (now superseded by GSR Part 2).
The objective of this Safety Guide is to set out a general scheme for classifying radioactive waste that is based primarily on considerations of long term safety, and thus, by implication, disposal of the waste. This Safety Guide, together with other IAEA safety standards on radioactive waste, assist in the development and implementation of appropriate waste management strategies and will facilitate communication and information exchange within and among States. Disposal is considered the final step in the management of radioactive waste, as stipulated in Safety Requirements publications on predisposal management of radioactive waste and disposal of radioactive waste. The Safety Guide identifies the conceptual boundaries between different classes of waste and provides guidance on their definition on the basis of long term safety considerations
This Safety Guide should be used in conjunction with the GS-R-2 (now superseded by GSR Part 7), which it supports. It provides generic criteria, and numerical values for these criteria, for protective actions and other response actions in the event of a nuclear or radiological emergency and gives recommendations on meeting the requirements of GS-R-2 (now superseded by GSR Part 7). This Safety Guide also presents operational criteria derived from certain generic criteria and as such represents the revision of the IAEA document on Intervention Criteria in a Nuclear or Radiation Emergency.

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