In response to an increase in global activities related to non-water-cooled reactors and small modular reactors, this new Safety Report documenting areas of novelty of these technologies when compared to the current fleet of reactors has been developed. The impact of these areas of novelty on the applicability and completeness of the IAEA safety standards is assessed in the publication. Gaps and areas for additional consideration are identified. The review undertaken to develop this report encompassed the safety standards related to the lifetime of these reactor technologies. The publication also considers the interface between safety, security, and safeguards in the design of these technologies.

• 1. INTRODUCTION
  • 1.1. Background
  • 1.2. Objective
  • 1.3. Scope
  • 1.4. Structure
• 2. IAEA APPROACH AND SAFETY STANDARDS
  • 2.1. Approach
    • 2.1.1. General
    • 2.1.2. Technologies considered
    • 2.1.3. Clarifications on terminology
  • 2.2. Structure of the iaea safety standards series
  • 2.3. Safety requirements considered
    • 2.3.1. Siting of nuclear installations
    • 2.3.2. Design and construction
    • 2.3.3. Commissioning and operation
    • 2.3.4. Nuclear fuel cycle facilities
    • 2.3.5. Radiation protection and safety
    • 2.3.6. Radioactive waste management and decommissioning
    • 2.3.7. Leadership and management for safety
    • 2.3.8. Safety assessment of nuclear installations
    • 2.3.9. Emergency preparedness and response
    • 2.3.10. Legal and regulatory framework
    • 2.3.11. Transport safety
  • 2.4. Safety guides considered
    • 2.4.1. Siting of nuclear installations
    • 2.4.2. Design
    • 2.4.3. Construction of nuclear installations
    • 2.4.4. Commissioning and operation
    • 2.4.5. Nuclear fuel cycle facilities
    • 2.4.6. Radiation protection and safety
    • 2.4.7. Radioactive waste management and decommissioning
    • 2.4.8. Leadership and management for safety
    • 2.4.9. Safety assessment of nuclear installations
    • 2.4.10. Emergency preparedness and response
    • 2.4.11. Legal and regulatory framework
    • 2.4.12. Transport safety
  • 2.5. Safety, security and safeguards interfaces
    • 2.5.1. The 3S concept
    • 2.5.2. Brief description of international safeguards framework
    • 2.5.3. Brief description of the security framework
• 3. IDENTIFICATION OF AREAS OF NOVELTY FOR EIDs
  • 3.1. Siting
    • 3.1.1. General areas of novelty
    • 3.1.2. Areas of novelty common to small size, multiple modules or modularity
    • 3.1.3. Areas of novelty specific to non-water cooled reactors
    • 3.1.4. Preliminary areas of novelty specific to transportable nuclear power plants
  • 3.2. Design
    • 3.2.1. General design approach
    • 3.2.2. Design of the core
    • 3.2.3. Design of the reactor vessel and the reactor coolant system (primary circuit)
    • 3.2.4. Design of the systems associated with the reactor coolant
    • 3.2.5. Design of the containment
    • 3.2.6. Design of electrical power systems
    • 3.2.7. Design of instrumentation and control systems
    • 3.2.8. Design of auxiliary and support systems
    • 3.2.9. Design against external hazards
  • 3.3. Construction
    • 3.3.1. General areas of novelty
    • 3.3.2. Areas of novelty common related to small size, multiple modules or modularity
    • 3.3.3. Areas of novelty specific to non-water cooled reactors
    • 3.3.4. Preliminary areas of novelty specific to transportable nuclear power plants
  • 3.4. Commissioning and operation
    • 3.4.1. General areas of novelty
    • 3.4.2. Areas of novelty specific to non-water cooled reactors
    • 3.4.3. Preliminary areas of novelty specific to transportable nuclear power plants
  • 3.5. Nuclear fuel cycle
    • 3.5.1. General areas of novelty
    • 3.5.2. Areas of novelty related to small size, multiple modules or modularity
    • 3.5.3. Areas of novelty specific to non-water cooled reactors
    • 3.5.4. Areas of novelty specific to transportable nuclear power plants
  • 3.6. Management of radioactive waste and spent fuel
    • 3.6.1. General areas of novelty
    • 3.6.2. Areas of novelty related to small size, multiple modules or modularity
    • 3.6.3. Areas of novelty specific to non-water cooled reactors
    • 3.6.4. Areas of novelty specific to transportable nuclear power plants
  • 3.7. Decommissioning
    • 3.7.1. General areas of novelty
    • 3.7.2. Areas of novelty related to small size, multiple modules or modularity
    • 3.7.3. Areas of novelty specific to non-water cooled reactors
    • 3.7.4. Areas of novelty specific to transportable nuclear power plants
  • 3.8. Emergency preparedness and response
    • 3.8.1. General areas of novelty
    • 3.8.2. Areas of novelty related to small size, multiple modules or modularity
    • 3.8.3. Areas of novelty specific to non-water cooled reactors
    • 3.8.4. Preliminary areas of novelty specific to transportable nuclear power plants
  • 3.9. Deployment models
    • 3.9.1. Areas of novelty related to small size, multiple modules or modularity
    • 3.9.2. Preliminary areas of novelty specific to transportable nuclear power plants
• 4. MAPPING OF APPLICATION OF SAFETY STANDARDS
  • 4.1. Introduction
  • 4.2. Siting
    • 4.2.1. IAEA Safety Standards Series No. SSR-1, Site Evaluation for Nuclear Installations
    • 4.2.2. IAEA Safety Standards Series No. SSG-35, Site Survey and Site Selection for Nuclear Installations
    • 4.2.3. IAEA Safety Standards Series No. SSG-79, Hazards Associated with Human Induced External Events in Site Evaluation for Nuclear Installations
    • 4.2.4. IAEA Safety Standards Series No. NS-G-3.2, Dispersion of Radioactive Material and Consideration of Population Distribution in Site Evaluation for Nuclear Power Plants
    • 4.2.5. IAEA Safety Standards Series No. NS-G-3.6, Geotechnical Aspects of Site Evaluation and Foundations for Nuclear Power Plants
    • 4.2.6. IAEA Safety Standards Series No. SSG-9 (Rev. 1), Seismic Hazards in Site Evaluation for Nuclear Installations
    • 4.2.7. IAEA Safety Standards Series No. SSG-18, Meteorological and Hydrological Hazards in Site Evaluation for Nuclear Installations
    • 4.2.8. IAEA Safety Standards Series No. SSG-21, Volcanic Hazards in Site Evaluation for Nuclear Installations
  • 4.3. Design
    • 4.3.1. IAEA Safety Standards Series No. SSR-2/1 (Rev. 1), Safety of Nuclear Power Plants: Design
    • 4.3.2. IAEA Safety Standards Series No. SSG-30, Safety Classification of Structures, Systems and Components in Nuclear Power Plants
    • 4.3.3. IAEA Safety Standards Series No. SSG-52, Design of the Reactor Core for Nuclear Power Plants
    • 4.3.4. IAEA Safety Standards Series No. SSG-56, Design of the Reactor Coolant System and Associated Systems for Nuclear Power Plants
    • 4.3.5. IAEA Safety Standards Series No. SSG-53, Design of the Reactor Containment and Associated Systems for Nuclear Power Plants
    • 4.3.6. IAEA Safety Standards Series No. SSG-34, Design of Electrical Power Systems for Nuclear Power Plants
    • 4.3.7. IAEA Safety Standards Series Nos SSG-39, Design of Instrumentation and Control Systems for Nuclear Power Plants, and SSG-51, Human Factors Engineering in the Design of Nuclear Power Plants
    • 4.3.8. IAEA Safety Standards Series No. SSG-62, Design of Auxiliary Systems and Supporting Systems for Nuclear Power Plants
    • 4.3.9. IAEA Safety Standards Series No. SSG-63, Design of Fuel Handling and Storage Systems for Nuclear Power Plants
    • 4.3.10. IAEA Safety Standards Series No. SSG-64, Protection Against Internal Hazards in the Design of Nuclear Power Plants
    • 4.3.11. IAEA Safety Standards Series No. SSG-68, External Events Excluding Earthquakes in the Design of Nuclear Power Plants
    • 4.3.12. IAEA Safety Standards Series No. SSG-67, Seismic Design and Qualification for Nuclear Power Plant
    • 4.3.13. IAEA Safety Standards Series No. SSG-69, Equipment Qualification for Nuclear Installations
    • 4.3.14. IAEA Safety Standards Series No. NS-G.1.13, Radiation Protection Aspects of Design for Nuclear Power Plants
  • 4.4. Construction
    • 4.4.1. IAEA Safety Standards Series No. SSG-38, Construction of Nuclear Installations
  • 4.5. Commissioning and operation
    • 4.5.1. IAEA Safety Standards Series No. SSR-2/2 (Rev. 1), Safety of Nuclear Power Plants: Commissioning and Operation
    • 4.5.2. IAEA Safety Standards Series No. SSG-28, Commissioning for Nuclear Power Plants
    • 4.5.3. IAEA Safety Standards Series No. SSG-76, Conduct of Operations at Nuclear Power Plants
    • 4.5.4. IAEA Safety Standards Series No. SSG-72, The Operating Organization for Nuclear Power Plants
    • 4.5.5. IAEA Safety Standards Series No. SSG-70, Operational Limits and Conditions and Operating Procedures for Nuclear Power Plants
    • 4.5.6. IAEA Safety Standards Series No. SSG-71, Modifications to Nuclear Power Plants
    • 4.5.7. IAEA Safety Standards Series No. SSG-73, Core Management and Fuel Handling for Nuclear Power Plants
    • 4.5.8. IAEA Safety Standards Series No. SSG-74, Maintenance, Testing, Surveillance and Inspection in Nuclear Power Plant
    • 4.5.9. IAEA Safety Standards Series No. SSG-75, Recruitment, Qualification and Training of Personnel for Nuclear Power Plants
    • 4.5.10. IAEA Safety Standards Series No. SSG-13, Chemistry Programme for Water Cooled Nuclear Power Plants
    • 4.5.11. IAEA Safety Standards Series No. SSG-48, Ageing Management and Development of a Programme for Long Term Operation of Nuclear Power Plants
    • 4.5.12. IAEA Safety Standards Series No. SSG-50, Operating Experience Feedback for Nuclear Installations
    • 4.5.13. IAEA Safety Standards Series No. SSG-77, Protection Against Internal and External Hazards in the Operation of Nuclear Power Plants
    • 4.5.14. IAEA Safety Standards Series No. SSG-54, Accident Management Programmes for Nuclear Power Plants
  • 4.6. Nuclear fuel cycle facilities
    • 4.6.1. IAEA Safety Standards Series No. SSR-4, Safety of Nuclear Fuel Cycle Facilities
    • 4.6.2. IAEA Safety Standards Series No. SSG-27 (Rev. 1), Criticality Safety in the Handling of Fissile Material
    • 4.6.3. IAEA Safety Standards Series Nos SSG-5 (Rev. 1), Safety of Conversion Facilities and Uranium Enrichment Facilities, SSG-6, Safety of Uranium Fuel Fabrication Facilities, SSG-7 (Rev. 1), Safety of Uranium and Plutonium Mixed Oxide Fuel Fabrication Facilities, and SSG-42, Safety of Nuclear Fuel Reprocessing Facilities
    • 4.6.4. IAEA Safety Standards Series No. SSG-43, Safety of Nuclear Fuel Cycle Research and Development Facilities
  • 4.7. Radiation protection and safety
    • 4.7.1. IAEA Safety Standards Series No. GSR Part 3, Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards
    • 4.7.2. IAEA Safety Standards Series No. GSG-7, Occupational Radiation Protection
    • 4.7.3. IAEA Safety Standards Series No. GSG-8, Radiation Protection of the Public and the Environment
    • 4.7.4. IAEA Safety Standards Series No. GSG-9, Regulatory Control of Radioactive Discharges to the Environment
    • 4.7.5. IAEA Safety Standards Series No. GSG-10, Prospective Radiological Environmental Impact Assessment for Facilities and Activities
    • 4.7.6. IAEA Safety Standards Series No. RS-G-1.7, Application of the Concepts of Exclusion, Exemption and Clearance
  • 4.8. Management of radioactive waste and spent fuel
    • 4.8.1. IAEA Safety Standards Series No. GSG-1, Classification of Radioactive Waste
    • 4.8.2. IAEA Safety Standards Series Nos GSR Part 5, SSG-40, SSG-41, SSG-45, WS-G-6.1 and GSG-3 on predisposal management of radioactive waste
    • 4.8.3. IAEA Safety Standards Series No. SSG-15 (Rev. 1), Storage of Spent Nuclear Fuel
    • 4.8.4. IAEA Safety Standards Series Nos SSR-5, SSG-1, SSG-14, SSG-23, SSG-29 and SSG-31 on the disposal of radioactive waste
    • 4.8.5. IAEA Safety Standards Series No. GSG-16, Leadership, Management and Culture for Safety in Radioactive Waste Management
  • 4.9. Decommissioning
    • 4.9.1. IAEA Safety Standards Series No. GSR Part 6, Decommissioning of Facilities
    • 4.9.2. IAEA Safety Standards Series No. SSG-47, Decommissioning of Nuclear Power Plants, Research Reactors and Other Nuclear Fuel Cycle Facilities
    • 4.9.3. IAEA Safety Standards Series No. WS-G-5.1, Release of Sites from Regulatory Control on Termination of Practices
    • 4.9.4. IAEA Safety Standards Series No. WS-G-5.2, Safety Assessment for the Decommissioning of Facilities Using Radioactive Material
  • 4.10. Leadership and management for safety
    • 4.10.1. IAEA Safety Standards Series No. GSR Part 2, Leadership and Management for Safety
    • 4.10.2. IAEA Safety Standards Series No. GS-G-3.1, Application of the Management System for Facilities and Activities
    • 4.10.3. IAEA Safety Standards Series No. GS-G-3.5, The Management System for Nuclear Installations
  • 4.11. Safety assessment
    • 4.11.1. IAEA Safety Standards Series No. GSR Part 4 (Rev. 1), Safety Assessment for Facilities and Activities
    • 4.11.2. IAEA Safety Standards Series No. SSG-2 (Rev. 1), Deterministic Safety Analysis for Nuclear Power Plants
    • 4.11.3. IAEA Safety Standards Series No. SSG-3, Development and Application of Level 1 Probabilistic Safety Assessment for Nuclear Power Plants
    • 4.11.4. IAEA Safety Standards Series No. SSG-4, Development and Application of Level 2 Probabilistic Safety Assessment for Nuclear Power Plants
    • 4.11.5. IAEA Safety Standards Series No. SSG-25, Periodic Safety Review for Nuclear Power Plants
    • 4.11.6. IAEA Safety Standards Series No. NS-G-2.13, Evaluation of Seismic Safety for Existing Nuclear Installations
  • 4.12. Emergency preparedness and response
    • 4.12.1. IAEA Safety Standards Series No. GSR Part 7, Preparedness and Response for a Nuclear and Radiological Emergency
    • 4.12.2. IAEA Safety Standards Series No. GS-G-2.1, Arrangements for Preparedness for a Nuclear or Radiological Emergency
    • 4.12.3. IAEA Safety Standards Series No. GSG-2, Criteria for Use in Preparedness and Response for a Nuclear or Radiological Emergency
    • 4.12.4. IAEA Safety Standards Series No. GSG-11, Arrangements for the Termination of a Nuclear or Radiological Emergency
    • 4.12.5. IAEA Safety Standards Series No. GSG-14, Arrangements for Public Communication in Preparedness and Response for a Nuclear or Radiological Emergency
    • 4.12.6. IAEA Safety Standards Series No. SSG-65, Preparedness and Response for a Nuclear or Radiological Emergency Involving the Transport of Radioactive Material
  • 4.13. Legal and regulatory framework
    • 4.13.1. IAEA Safety Standards Series No. GSR Part 1 (Rev. 1), Governmental, Legal and Regulatory Framework for Safety
    • 4.13.2. IAEA Safety Standards Series No. GSG-12, Organization, Management and Staffing of the Regulatory Body for Safety
    • 4.13.3. IAEA Safety Standards Series No. GSG-13, Functions and Processes of the Regulatory Body for Safety
    • 4.13.4. IAEA Safety Standards Series No. SSG-12, Licensing Process for Nuclear Installations
    • 4.13.5. IAEA Safety Standards Series No. GSG-6, Communication and Consultation with Interested Parties by the Regulatory Body
    • 4.13.6. IAEA Safety Standards Series No. SSG-16 (Rev. 1), Establishing the Safety Infrastructure for a Nuclear Power Programme
  • 4.14. Transport of radioactive material
    • 4.14.1. IAEA Safety Standards Series No. SSR-6 (Rev. 1), Regulations for the Safe Transport of Radioactive Material
• 5. SAFETY, SECURITY AND SAFEGUARDS INTERFACES FOR EIDs
  • 5.1. Safeguards considerations
    • 5.1.1. Transportability and modularity of reactors with the fuel loaded
    • 5.1.2. Transport of nuclear fuel
    • 5.1.3. Small size of fuel items
    • 5.1.4. New fuels and fuel cycles
    • 5.1.5. Limited access
    • 5.1.6. Remote locations and autonomous operations
    • 5.1.7. Non-electrical end use and intermittent operations
    • 5.1.8. Moving-fuel reactors and continuous on-line refuelling
    • 5.1.9. Lack of measurement technologies and other verification techniques
  • 5.2. Security considerations
    • 5.2.1. Design basis threat and physical protection systems
    • 5.2.2. Transportability
    • 5.2.3. Remote locations
    • 5.2.4. Non-electrical applications, location in urban areas
    • 5.2.5. Compact layout of EIDs and underground location
    • 5.2.6. Protection requirements for new types of fuel and new fuel cycles
    • 5.2.7. Graded approach based on potential consequences
    • 5.2.8. Insider threats
    • 5.2.9. Cybersecurity considerations for EIDs
  • 5.3. Safety, security and safeguards interfaces: Potential synergies and challenges
    • 5.3.1. General
    • 5.3.2. The safety–security interface
    • 5.3.3. The security–safeguards interface
    • 5.3.4. The safeguards–safety interface
• 6. KEY OUTCOMES OF THE APPLICABILITY REVIEW OF SAFETY STANDARDS
• Appendix IOVERVIEW OF SAFEGUARDS CHALLENGES
• Appendix IISUMMARY TABLES
• REFERENCES
• ABBREVIATIONS
• CONTRIBUTORS TO DRAFTING AND REVIEW