This publication provides detailed information for operating organizations of research reactors on methodologies to manage existing and potential ageing effects and the degradation of structures, systems and components. Practical guidance is presented on managing the effects of ageing on civil structures, on mechanical, electrical and instrumentation and control systems, and on reactor components important for safety and operation. This publication also provides information on how to establish and implement an effective and systematic ageing management programme, including the management of modifications, modernizations and refurbishments. Several practical examples of successful ageing management programmes executed in operating research reactors are included as annexes.

• 1. INTRODUCTION
  • 1.1. Background
  • 1.2. Objective
  • 1.3. Scope
  • 1.4. Structure
• 2. FACTORS TO BE CONSIDERED FOR AN AGEING MANAGEMENT PROGRAMME
  • 2.1. General
  • 2.2. Definition of ageing
  • 2.3. Degradation mechanisms and ageing effects
    • 2.3.1. Operating conditions and obsolescence
    • 2.3.2. Degradation of material characteristics
  • 2.4. Safety requirements and ageing
    • 2.4.1. Safety objective
    • 2.4.2. Ageing and defence in depth
    • 2.4.3. Ageing and reliability
    • 2.4.4. Ageing and advances in technology and safety requirements
  • 2.5. Service conditions and ageing
    • 2.5.1. Normal operation
    • 2.5.2. Anticipated operational occurrences
    • 2.5.3. External conditions
  • 2.6. Physical factors of ageing
    • 2.6.1. Radiation effects
    • 2.6.2. Temperature and pressure
    • 2.6.3. Vibration and cyclic loading
    • 2.6.4. Corrosion
    • 2.6.5. Erosion
    • 2.6.6. Other chemical reactions
  • 2.7. Non-physical factors of ageing
    • 2.7.1. Changes in technology
    • 2.7.2. Changes in safety requirements
    • 2.7.3. Out of date documentation
    • 2.7.4. Inadequacies in design
    • 2.7.5. Improper maintenance and testing
  • 2.8. Ageing issues for research reactors
• 3. DEVELOPING AN AGEING MANAGEMENT PROGRAMME
  • 3.1. Introduction
  • 3.2. Administration and organization
    • 3.2.1. Planning
    • 3.2.2. Communication
    • 3.2.3. Training and qualification
  • 3.3. Screening and selection of structures, systems and components
    • 3.3.1. The first stage of the screening process
    • 3.3.2. The second stage of the screening process
    • 3.3.3. Alternative screening methodologies
  • 3.4. Ageing management review of screened structures, systems and components
    • 3.4.1. Procedure to prepare an ageing management review
  • 3.5. Identification and understanding of degradation mechanisms
  • 3.6. Detection, monitoring and trending of ageing effects
    • 3.6.1. Inspection methods
  • 3.7. Collection of relevant data and evaluation
  • 3.8. Minimization and mitigation of ageing effects
    • 3.8.1. Minimization
    • 3.8.2. Mitigation
  • 3.9. Acceptance criteria
  • 3.10. Assessment of residual life, including time limited ageing analysis
  • 3.11. Corrective actions
  • 3.12. Documentation and record keeping
  • 3.13. Implementing an ageing management programme
  • 3.14. Review and continuous improvement of the ageing management programme
• 4. AGEING MANAGEMENT OF STRUCTURES, SYSTEMS AND COMPONENTS
  • 4.1. Introduction
  • 4.2. Civil structures
  • 4.3. Electrical components
    • 4.3.1. Battery banks
    • 4.3.2. Battery chargers and converters
    • 4.3.3. Inverters
    • 4.3.4. Equipment specific DC power supplies
    • 4.3.5. Circuit breakers and switchgears
    • 4.3.6. Relays
    • 4.3.7. Variable frequency drives
    • 4.3.8. Transformers
    • 4.3.9. Electrical motors
    • 4.3.10. Lightning protection and earthing or grounding
    • 4.3.11. Power cables
  • 4.4. Mechanical components
    • 4.4.1. Reactor vessel or tank
    • 4.4.2. Connections and penetrations
    • 4.4.3. Core components and support structures
    • 4.4.4. Heat exchangers
    • 4.4.5. Major pumps
    • 4.4.6. Control and safety rods
    • 4.4.7. Piping
    • 4.4.8. Valves
  • 4.5. Instrumentation and control systems
    • 4.5.1. Nuclear measurements (neutron, alpha, beta and gamma radiation)
    • 4.5.2. Process instrumentation (temperature, pressure, flow)
    • 4.5.3. Relays
    • 4.5.4. Computer based systems
    • 4.5.5. Radiation monitoring
    • 4.5.6. Signal cables
  • 4.6. Experimental devices
  • 4.7. Auxiliary systems
    • 4.7.1. Ventilation system (containment/confinement functions)
    • 4.7.2. Diesel generators (emergency power)
    • 4.7.3. Compressors (including air drums and receivers)
    • 4.7.4. Waste handling (liquid, gas, solid)
    • 4.7.5. Spent fuel storage
    • 4.7.6. Water purification
    • 4.7.7. Cranes and material handling devices
    • 4.7.8. Fire protection systems
    • 4.7.9. Tanks and vessels
    • 4.7.10. Cooling towers
    • 4.7.11. Hot cell facilities
    • 4.7.12. Fuel handling equipment
• 5. MANAGEMENT OF MODIFICATION, MODERNIZATION AND REFURBISHMENT PROJECTS
  • 5.1. Introduction
  • 5.2. Initiating the modification, modernization or refurbishment project
    • 5.2.1. Justification of the project
    • 5.2.2. Objective
    • 5.2.3. Safety assessment, analysis and review
  • 5.3. Planning the modification, modernization or refurbishment project
    • 5.3.1. Scope statement
    • 5.3.2. Work breakdown structure and schedule
    • 5.3.3. Budget content
    • 5.3.4. Risk management
    • 5.3.5. Complete project baseline
  • 5.4. Executing and monitoring the modification, modernization or refurbishment project
    • 5.4.1. Design phase
    • 5.4.2. Procurement phase
    • 5.4.3. Installation phase
    • 5.4.4. Performance verification (commissioning/operability testing) phase
  • 5.5. Close out of the modification, modernization or refurbishment project
    • 5.5.1. Project report
    • 5.5.2. Updating of records
    • 5.5.3. Temporary arrangements
    • 5.5.4. Lessons identified
• AppendixAGEING MANAGEMENT OF STRUCTURES, SYSTEMS AND COMPONENTS
• REFERENCES
• Annex IAGEING MANAGEMENT PROGRAMME AND ITS IMPLEMENTATION FOR THE TRIGA MARK II RESEARCH REACTOR AT THE LABORATORY OF APPLIED NUCLEAR ENERGY (LENA), UNIVERSITY OF PAVIA, ITALY
• Annex IIAGEING MANAGEMENT ACTIVITIES AT ARGENTINE RESEARCH REACTOR RA-6
• Annex IIIAGEING MANAGEMENT PROGRAMME FOR THE SAFARI-1 RESEARCH REACTOR
• Annex IVAGEING MANAGEMENT PROGRAMME FOR THE BR2 RESEARCH REACTOR
• ABBREVIATIONS
• CONTRIBUTORS TO DRAFTING AND REVIEW
• STRUCTURE OF THE IAEA NUCLEAR ENERGY SERIES