International Atomic Energy Agency

(Міжнародна Агенція з Атомної Енергії)

http://www.iaea.org/

МАГАТЕ (IAEA)
WENRA
ETSON
European Union (EU)

 Safety Standards 


Requirements: Guides:


 Fasilities and activities 






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Serial №
Title

Serial № Title (126)  

 IAEA Safety Glossary
GSG-1Classification of Radioactive Waste
GSG-10Prospective Radiological Environmental Impact Assessment for Facilities and Activities
GSG-11Arrangements for the Termination of a Nuclear of Radiological Emergency
GSG-12Organization, Management and Staffing of the Regulatory Body for Safety
GSG-13Functions and Processes of the Regulatory Body for Safety
GSG-2Criteria for Use in Preparedness and Response for a Nuclear or Radiological Emergency
GS-G-2.1Arrangements for Preparedness for a Nuclear or Radiological Emergency
GSG-3The Safety Case and Safety Assessment for the Predisposal Management of Radioactive Waste
GS-G-3.1Application of the Management System for Facilities and Activities
GS-G-3.3The Management System for the Processing, Handling and Storage of Radioactive Waste
GS-G-3.4 The Management System for the Disposal of Radioactive Waste
GS-G-3.5 The Management System for Nuclear Installations
GS-G-4.1 Format and Content of the Safety Analysis Report for Nuclear Power Plants
GSG-6Communication and Consultation with Interested Parties by the Regulatory Body
GSG-7Occupational Radiation Protection
GSG-8Radiation Protection of the Public and the Environment
GSG-9Regulatory Control of Radioactive Discharges to the Environment
GSR Part 1 (Rev. 1)Governmental, Legal and Regulatory Framework for Safety
GSR Part 2Leadership and Management for Safety
GSR Part 3 Radiation Protection and Safety of Radiation Sources. International BSS
GSR Part 4 (Rev. 1)Safety Assessment for Facilities and Activities
GSR Part 5Predisposal Management of Radioactive Waste
GSR Part 6Decommissioning of Facilities
GSR Part 7Preparedness and Response for a Nuclear or Radiological Emergency
NS-G-1.10 Design of Reactor Containment Systems for Nuclear Power Plants
NS-G-1.11 Protection against Internal Hazards other than Fires and Explosions in the Design of Nuclear Power Plants
NS-G-1.12 Design of the Reactor Core for Nuclear Power Plants
NS-G-1.13Radiation Protection Aspects of Design for Nuclear Power Plants
NS-G-1.4 Design of Fuel Handling and Storage Systems in Nuclear Power Plants
NS-G-1.5 External Events Excluding Earthquakes in the Design of Nuclear Power Plants
NS-G-1.6 Seismic Design and Qualification for Nuclear Power Plants
NS-G-1.7 Protection Against Internal Fires and Explosions in the Design of Nuclear Power Plants
NS-G-1.9 Design of the Reactor Coolant System and Associated Systems in Nuclear Power Plants
NS-G-2.1 Fire Safety in the Operation of Nuclear Power Plants
NS-G-2.13 Evaluation of Seismic Safety for Existing Nuclear Installations
NS-G-2.14 Conduct of Operations at Nuclear Power Plants
NS-G-2.2 Operational Limits and Conditions and Operating Procedures for Nuclear Power Plants
NS-G-2.3 Modifications to Nuclear Power Plants
NS-G-2.4 The Operating Organization for Nuclear Power Plants
NS-G-2.5 Core Management and Fuel Handling for Nuclear Power Plants
NS-G-2.6 Maintenance, Surveillance and In-Service Inspection in Nuclear Power Plants
NS-G-2.8 Recruitment, Qualification and Training of Personnel for Nuclear Power Plants
NS-G-3.1 External Human Induced Events in Site Evaluation for Nuclear Power Plants
NS-G-3.6 Geotechnical Aspects of Site Evaluation and Foundations for Nuclear Power Plants
NS-G-4.1 Commissioning of Research Reactors
NS-G-4.2 Maintenance, Periodic Testing and Inspection of Research Reactors
NS-G-4.3 Core Management and Fuel Handling for Research Reactors
NS-G-4.4 Operational Limits and Conditions and Operating Procedures for Research Reactors
NS-G-4.5 The Operating Organization and the Recruitment, Training and Qualification of Personnel for Research Reactors
NS-G-4.6 Radiation Protection and Radioactive Waste Management in the Design and Operation of Research Reactors
NS-R-5 Safety of Nuclear Fuel Cycle Facilities
RS-G-1.10 Safety of Radiation Generators and Sealed Radioactive Sources
RS-G-1.7 Application of the Concepts of Exclusion, Exemption and Clearance
RS-G-1.8Environmental and Source Monitoring for Purposes of Radiation Protection
RS-G-1.9Categorization of Radioactive Sources
SF-1Fundamental Safety Principles
SSG-1 Borehole Disposal Facilities for Radioactive Waste
SSG-10 Ageing Management for Research Reactors
SSG-11 Radiation Safety in Industrial Radiography
SSG-13 Chemistry Programme for Water Cooled Nuclear Power Plants
SSG-14 Geological Disposal Facilities for Radioactive Waste
SSG-15 Storage of Spent Nuclear Fuel
SSG-16 Establishing the Safety Infrastructure for a Nuclear Power Programme
SSG-17 Control of Orphan Sources and Other Radioactive Material in the Metal Recycling and Production Industries
SSG-18 Meteorological and Hydrological Hazards in Site Evaluation for Nuclear Installations
SSG-19 National Strategy for Regaining Control over Orphan Sources and Improving Control over Vulnerable Sources
SSG-2Deterministic Safety Analysis for Nuclear Power Plants
SSG-20 Safety Assessment for Research Reactors and Preparation of the Safety Analysis Report
SSG-21 Volcanic Hazards in Site Evaluation for Nuclear Installations
SSG-22 Use of a Graded Approach in the Application of the Safety Requirements for Research Reactors
SSG-23 The Safety Case and Safety Assessment for the Disposal of Radioactive Waste
SSG-24 Safety in the Utilization and Modification of Research Reactors
SSG-25 Periodic Safety Review for Nuclear Power Plants
SSG-26Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material (2012 Edition)
SSG-27 Criticality Safety in the Handling of Fissile Material
SSG-28Commissioning for Nuclear Power Plants
SSG-29Near Surface Disposal Facilities for Radioactive Waste
SSG-3 Development and Application of Level 1 Probabilistic Safety Assessment for Nuclear Power Plants
SSG-30 Safety Classification of Structures, Systems and Components in Nuclear Power Plants
SSG-31 Monitoring and Surveillance of Radioactive Waste Disposal Facilities
SSG-32Protection of the Public against Exposure Indoors due to Radon and Other Natural Sources of Radiation
SSG-33Schedules of Provisions of the IAEA Regulations for the Safe Transport of Radioactive Material, 2012 Edition
SSG-34Design of Electrical Power Systems for Nuclear Power Plants
SSG-35Site Survey and Site Selection for Nuclear Installations
SSG-36Radiation Safety for Consumer Products
SSG-37Instrumentation and Control Systems and Software Important to Safety for Research Reactors
SSG-38Construction for Nuclear Installations
SSG-39Design of Instrumentation and Control Systems for Nuclear Power Plants
SSG-4 Development and Application of Level 2 Probabilistic Safety Assessment for Nuclear Power Plants
SSG-40Predisposal Management of Radioactive Waste from Nuclear Power Plants and Research Reactors Specific Safety Guide
SSG-41Predisposal Management of Radioactive Waste from Nuclear Fuel Cycle Facilities
SSG-42Safety of Nuclear Fuel Reprocessing Facilities
SSG-43Safety of Nuclear Fuel Cycle Research and Development Facilities
SSG-44Establishing the Infrastructure for Radiation Safety
SSG-45Predisposal Management of Radioactive Waste from the Use of Radioactive Material in Medicine, Industry, Agriculture, Research and Education
SSG-46Radiation Protection and Safety in Medical Uses of Ionizing Radiation
SSG-47Decommissioning of Nuclear Power Plants, Research Reactors and Other Nuclear Fuel Cycle Facilities
SSG-48Ageing Management and Development of a Programme for Long Term Operation of Nuclear Power Plants Ageing Management and Development of a Programme for Long Term Operation of Nuclear Power Plants
SSG-49Decommissioning of Medical, Industrial and Research Facilities
SSG-5 Safety of Conversion Facilities and Uranium Enrichment Facilities
SSG-50Operating Experience Feedback for Nuclear Installations
SSG-51Human Factors Engineering in Nuclear Power Plants
SSG-54Accident Management Programmes for Nuclear Power Plants
SSG-6 Safety of Uranium Fuel Fabrication Facilities
SSG-7 Safety of Uranium and Plutonium Mixed Oxide Fuel Fabrication Facilities
SSG-8 Radiation Safety of Gamma, Electron and X Ray Irradiation Facilities
SSG-9 Seismic Hazards in Site Evaluation for Nuclear Installations Specific
SSR-1Site Evaluation for Nuclear Installations
SSR-2/1 (Rev. 1)Safety of Nuclear Power Plants: Design
SSR-2/2 (Rev. 1)Safety of Nuclear Power Plants: Commissioning and Operation
SSR-3Safety of Research Reactors
SSR-4Safety of Nuclear Fuel Cycle Facilities
SSR-5 Disposal of Radioactive Waste
SSR-6 (Rev. 1)Regulations for the Safe Transport of Radioactive Material - 2012 Edition
SSR-6 (Rev.1)Regulations for the Safe Transport of Radioactive Material (2018 Edition)
TS-G-1.2Planning and Preparing for Emergency Response to Transport Accidents Involving Radioactive Material
TS-G-1.3 Radiation Protection Programmes for the Transport of Radioactive Material
TS-G-1.4 The Management System for the Safe Transport of Radioactive Material
TS-G-1.5 Compliance Assurance for the Safe Transport of Radioactive Material
TS-G-1.6 (Rev.1)Schedules of Provisions of the IAEA Regulations for the Safe Transport of Radioactive Material (2009 Edition)
WS-G-1.2 Management of Radioactive Waste from the Mining and Milling of Ores
WS-G-3.1Remediation Process for Areas Affected by Past Activities and Accidents
WS-G-5.1Release of Sites from Regulatory Control on Termination of Practices
WS-G-5.2Safety Assessment for the Decommissioning of Facilities Using Radioactive Material
WS-G-6.1Storage of Radioactive Waste