International Atomic Energy Agency

(Міжнародна Агенція з Атомної Енергії)

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 _Новий_документ_(on_gonchar)_13.09.2017 09:02:58
 IAEA Safety Glossary
GSG-1Classification of Radioactive Waste
GS-G-1.1 Organization and Staffing of the Regulatory Body for Nuclear Facilities
GS-G-1.2 Review and Assessment of Nuclear Facilities by the Regulatory Body
GS-G-1.3 Regulatory Inspection of Nuclear Facilities and Enforcement by the Regulatory Body
GS-G-1.4 Documentation for Use in Regulating Nuclear Facilities
GS-G-1.5 Regulatory Control of Radiation Sources
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
GSG-3 The 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-3.2The Management System for Technical Services in Radiation Safety
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
GSG-4Use of External Experts by the Regulatory Body
GS-G-4.1 Format and Content of the Safety Analysis Report for Nuclear Power Plants
GSG-5Justification of Practices, Including Non-medical Human Imaging
GSG-6Communication and Consultation with Interested Parties by the Regulatory Body
GSR Part 1Governmental, 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 4Safety 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-1.8 Design of Emergency Power Systems for 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-2.11 A System for the Feedback of Experience from Events in Nuclear Installations
NS-G-2.12 Ageing Management for 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-2.15 Severe Accident Management Programmes for 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-2.7 Radiation Protection and Radioactive Waste Management in the Operation of Nuclear Power Plants
NS-G-2.8 Recruitment, Qualification and Training of Personnel for Nuclear Power Plants
NS-G-2.9 Commissioning for Nuclear Power Plants
NS-G-3.1 External Human Induced Events in Site Evaluation for Nuclear Power Plants
NS-G-3.2 Dispersion of Radioactive Material in Air and Water and Consideration of Population Distribution in Site Evaluation for Nuclear Power Plant
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-3Site Evaluation for Nuclear Installations
NS-R-5 Safety of Nuclear Fuel Cycle Facilities
RS-G-1.1Occupational Radiation Protection
RS-G-1.10 Safety of Radiation Generators and Sealed Radioactive Sources
RS-G-1.2Assessment of Occupational Exposure Due to Intakes of Radionuclides
RS-G-1.3Assessment of Occupational Exposure Due to External Sources of Radiation
RS-G-1.4Building Competence in Radiation Protection and the Safe Use of Radiation Sources
RS-G-1.5 Radiological Protection for Medical Exposure to Ionizing Radiation
RS-G-1.6 Occupational Radiation Protection in the Mining and Processing of Raw Materials
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-12 Licensing Process for Nuclear Installations
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-2 Deterministic 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-5 Safety of Conversion Facilities and Uranium Enrichment Facilities
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-2/1Safety of Nuclear Power Plants: Design
SSR-2/2Safety 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 Regulations for the Safe Transport of Radioactive Material - 2012 Edition
TS-G-1.1 (rev.1) Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material
TS-G-1.1 (ST-2) Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material
TS-G-1.2 (ST-3) Planning 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)
TS-R-1Regulations for the Safe Transport of Radioactive Material, 2009 Edition
TS-R-1 Regulations for the Safe Transport of Radioactive Material, 1996 Edition (As Amended 2003)
TS-R-1 Regulations for the Safe Transport of Radioactive Material, 1996 Edition (Revised)
TS-R-1 Regulations for the Safe Transport of Radioactive Material, 2005 Edition
WS-G-1.2 Management of Radioactive Waste from the Mining and Milling of Ores
WS-G-2.1 Decommissioning of Nuclear Power Plants and Research Reactors
WS-G-2.2 Decommissioning of Medical, Industrial and Research Facilities
WS-G-2.3Regulatory Control of Radioactive Discharges to the Environment
WS-G-2.4 Decommissioning of Nuclear Fuel Cycle Facilities
WS-G-2.5Predisposal Management of Low and Intermediate Level Radioactive Waste
WS-G-2.6Predisposal Management of High Level Radioactive Waste
WS-G-2.7 Management of Waste from the Use of Radioactive Material in Medicine, Industry, Agriculture, Research and Education
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