This publication provides an introduction to the management of research reactor spent nuclear fuel (RRSNF). Five key areas are discussed: types of RRSNF, characterization data, wet storage considerations, dry storage considerations, and lessons learned and current practices. Information on internationally accepted standards as well as information on aspects such as drying treatment and surveillance programmes are presented, as well as suggestions for further optimization of effective and safe storage of RRSNF through the application of new approaches. The intended users of this publication include industry professionals at operating research reactors and at RRSNF storage facilities who need to identify the most suitable approach for interim storage of spent fuel.

• 1. INTRODUCTION
  • 1.1. Background
    • 1.1.1. Options for the management of spent nuclear fuel from research reactors
    • 1.1.2. Current situation of research reactors and spent fuel storage
  • 1.2. Objectives
  • 1.3. Scope
  • 1.4. Structure
• 2. WET STORAGE OF RESEARCH REACTOR SPENT FUEL
  • 2.1. Wet storage technology
    • 2.1.1. Corrosion in wet storage
    • 2.1.2. Performance of spent nuclear fuel and lifetime prediction models
  • 2.2. Wet storage facility considerations
    • 2.2.1. Storage pool structure
    • 2.2.2. Pool liners and coatings
    • 2.2.3. Double walled containment
    • 2.2.4. Considerations about accessibility for surveillance, maintenance and repair
  • 2.3. Storage pool maintenance
    • 2.3.1. Pool cleaning — filtering and deionization systems
    • 2.3.2. Pool cleaning — sludge removal and vacuuming
  • 2.4. Storage pool inspection and surveillance
    • 2.4.1. Inspection of pool structural integrity
    • 2.4.2. Coating integrity
    • 2.4.3. Stainless steel liner integrity
    • 2.4.4. Aluminium liner integrity
    • 2.4.5. Leak detection
    • 2.4.6. In-service inspection
    • 2.4.7. Inspection of spent nuclear fuel racks and baskets
    • 2.4.8. Inaccessible structures
  • 2.5. Facility lifetime extension
    • 2.5.1. Recoating
    • 2.5.2. Leak repair
• 3. TRANSITION FROM WET TO DRY STORAGE
  • 3.1. Predrying conditioning
  • 3.2. Drying of spent nuclear fuel for transitioning to dry storage
    • 3.2.1. Water forms
    • 3.2.2. Drying technologies
    • 3.2.3. Dryness verification
  • 3.3. Inert gas considerations
• 4. DRY STORAGE OF RESEARCH REACTOR SPENT FUEL
  • 4.1. Dry storage technology
    • 4.1.1. Dry storage options and technologies
    • 4.1.2. Operational and economic considerations
    • 4.1.3. Licensed dry storage systems
    • 4.1.4. Sealed and vented technologies
    • 4.1.5. Technical considerations for dry storage
    • 4.1.6. Hydrogen buildup
    • 4.1.7. Generation of pyrophoric uranium hydride
    • 4.1.8. Retrievability considerations
    • 4.1.9. Dry storage acceptance criteria and operational envelope
  • 4.2. Dry storage package design considerations
    • 4.2.1. Material selection
    • 4.2.2. Canister and package design
  • 4.3. Dry storage system infrastructure
    • 4.3.1. Facility surveillance and maintenance
    • 4.3.2. Lifetime management and in-service inspection
    • 4.3.3. Lifetime extension beyond design life
  • 4.4. Operational considerations for dry storage
    • 4.4.1. Container surveillance
    • 4.4.2. Documentation and record retention
• 5. CHARACTERIZATION FOR STORAGE
  • 5.1. Fuel data needs
    • 5.1.1. Design data
    • 5.1.2. Post-discharge nuclear data
    • 5.1.3. Physical condition
  • 5.2. Baseline characterization needs
    • 5.2.1. Baseline characterization for wet storage
    • 5.2.2. Baseline characterization for dry storage
    • 5.2.3. Baseline characterization for overpacking
  • 5.3. Characterization tools
    • 5.3.1. Physical measurement tools
    • 5.3.2. Computer simulation tools
  • 5.4. Fuel condition assessment
    • 5.4.1. Visual inspections
    • 5.4.2. Sip testing
    • 5.4.3. Data needed to characterize physical condition
• 6. SAFETY ISSUES FOR RESEARCH REACTOR SPENT FUEL STORAGE
  • 6.1. Safety Guide on storage of spent nuclear fuel
  • 6.2. Regulatory requirements
  • 6.3. Commissioning
  • 6.4. Physical protection
  • 6.5. Safeguards
  • 6.6. Emergency planning
  • 6.7. Decommissioning
• 7. LESSONS LEARNED FROM RESEARCH REACTOR SPENT FUEL STORAGE
  • 7.1. Centralized wet storage at Savannah River Site
    • 7.1.1. L-Basin facility description
    • 7.1.2. Good practices at the L-Basin
    • 7.1.3. Conclusions
  • 7.2. Centralized dry storage at HABOG
    • 7.2.1. HABOG facility description
    • 7.2.2. Good practices at HABOG
    • 7.2.3. Conclusions
  • 7.3. Wet and semidry storage at the Budapest Research Reactor
    • 7.3.1. Description of the Budapest Research Reactor
    • 7.3.2. Good practices at the Budapest Research Reactor
    • 7.3.3. Conclusions
  • 7.4. Wet storage remediation at Vinča Institute of Nuclear Sciences
    • 7.4.1. Description of the RA research reactor
    • 7.4.2. Wet storage remediation activities
    • 7.4.3. Conclusions
• 8. CONCLUSIONS
• REFERENCES
• ABBREVIATIONS
• CONTRIBUTORS TO DRAFTING AND REVIEW
• STRUCTURE OF THE IAEA NUCLEAR ENERGY SERIES