Ageing Management for Research Reactors  
Published by International Atomic Energy Agency
Publication Date:  Available in all formats
ISBN: 9789201032232
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This Safety Guide provides practical guidance and recommendations on ageing management for research reactors, to meet the relevant requirements of IAEA Safety Standards Series No. SSR-3, Safety of Research Reactors. It is intended for use by operating organizations in establishing, implementing and improving ageing management programmes for research reactors, and by regulatory bodies in verifying that ageing of research reactors is being effectively managed. The Safety Guide focuses on managing the physical ageing of systems, structures and components important to safety, and also provides guidance on safety aspects of managing obsolescence. This Safety Guide is a revision of IAEA Safety Standards Series No. SSG-10, which it supersedes.
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This Safety Guide provides practical guidance and recommendations on ageing management for research reactors, to meet the relevant requirements of IAEA Safety Standards Series No. SSR-3, Safety of Research Reactors. It is intended for use by operating organizations in establishing, implementing and improving ageing management programmes for research reactors, and by regulatory bodies in verifying that ageing of research reactors is being effectively managed. The Safety Guide focuses on managing the physical ageing of systems, structures and components important to safety, and also provides guidance on safety aspects of managing obsolescence. This Safety Guide is a revision of IAEA Safety Standards Series No. SSG-10, which it supersedes.
Table of contents
  • 1. INTRODUCTION
    • Background
    • Objective
    • Scope
    • Structure
  • 2. APPLICATION OF THE MANAGEMENT SYSTEM TO AGEING MANAGEMENT AT A RESEARCH REACTOR
    • Management responsibility for ageing management at a research reactor
    • Resource management for ageing management at a research reactor
    • Process implementation for ageing management at a research reactor
    • Measurement, assessment and improvement of the management system for ageing management at a research reactor
  • 3. THE EFFECTS OF AGEING ON THE SAFETY OF RESEARCH REACTORS
    • Ageing processes at research reactors
    • Ageing and defence in depth at a research reactor
    • Service conditions and ageing at a research reactor
  • 4. AGEING MANAGEMENT CONSIDERATIONS IN DIFFERENT STAGES OF THE LIFETIME OF A RESEARCH REACTOR
    • Ageing management considerations in the design of a research reactor
      • Reactor design considerations
    • Ageing management considerations in the fabrication and construction of a research reactor
    • Ageing management considerations in the commissioning of a research reactor
    • Ageing management considerations in the operation of a research reactor
    • Ageing management considerations in the utilization and modification of a research reactor
    • Ageing management considerations in the extended shutdown of a research reactor
    • Ageing management considerations in planning for decommissioning of a research reactor
  • 5. AGEING MANAGEMENT PROGRAMMES FOR RESEARCH REACTORS
    • Screening of structures, systems and components at a research reactor for the ageing management programme
    • Identification and understanding of degradation mechanisms at a research reactor
    • Minimization of ageing effects at a research reactor
    • Detection, monitoring and identification of trends in ageing effects at a research reactor
    • Mitigation of ageing effects at a research reactor
    • Acceptance criteria for ageing management at a research reactor
    • Corrective actions for ageing management at a research reactor
    • Review and improvement of the ageing management programme at a research reactor
    • Record keeping for ageing management at a research reactor
  • 6. MANAGEMENT OF OBSOLESCENCE AT RESEARCH REACTORS
  • 7. INTERFACES BETWEEN AGEING MANAGEMENT AND OTHER PROGRAMMES AND TECHNICAL AREAS AT A RESEARCH REACTOR
    • Interface between ageing management and maintenance, periodic testing and inspection at a research reactor
    • Interface between ageing management and periodic safety review of a research reactor
    • Interface between ageing management and equipment qualification at a research reactor
    • Interface between ageing management and reconstitution of the design basis for structures, systems and components at a research reactor
    • Interface between ageing management and configuration management at a research reactor
    • Time limited ageing analyses at a research reactor
    • Interface between ageing management and the continued safe operation of a research reactor
    • Interface between ageing management and post-service surveillance and testing at a research reactor
    • Interface between ageing management and operational limits and conditions at a research reactor
    • Interfaces between ageing management and safety and nuclear security at a research reactor
  • REFERENCES
  • Annex I EFFECT OF AGEING FOR DIFFERENT SERVICE CONDITIONS
  • Annex II EXAMPLE OF SCREENING OF RESEARCH REACTOR STRUCTURES, SYSTEMS AND COMPONENTS FOR AGEING MANAGEMENT PURPOSES
  • CONTRIBUTORS TO DRAFTING AND REVIEW
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