In the context of the safe management of disused sealed radioactive sources, an important and emerging issue of immediate concern is the management of depleted uranium (DU) contained in radiation shielding materials, as potential radioactive waste. This publication presents relevant information on technical issues and factors, as well as specific Member State experiences leading to the identification of potential options for the management of DU shields. Various options for safe, secure and cost-effective solutions have been explored, ranging from returning to manufacturer, including reuse, recycling, storage and disposal in licensed facilities.

• 1. INTRODUCTION
  • 1.1. Background
  • 1.2. Objective
  • 1.3. Scope
  • 1.4. Structure
• 2. CHARACTERISTICS OF URANIUM AND DU
  • 2.1. Characteristics of uranium
  • 2.2. Characteristics of DU
    • 2.2.1. General characteristics of DU
    • 2.2.2. Chemical characteristics of DU
    • 2.2.3. Radiological characteristics of DU
• 3. USES OF DU
  • 3.1. Devices that contain DU
    • 3.1.1. Teletherapy devices
    • 3.1.2. Brachytherapy devices
    • 3.1.3. Self-shielded irradiators
    • 3.1.4. Industrial gamma radiography
    • 3.1.5. Measurement gauges
    • 3.1.6. Well logging devices
    • 3.1.7. Containers and packages
    • 3.1.8. Linear accelerators
• 4. HOW TO IDENTIFY DEVICES CONTAINING DU
  • 4.1. Device labelling information
  • 4.2. Device documentation
  • 4.3. Device examination to determine if it contains DU
• 5. SAFEGUARDS CONSIDERATIONS FOR DU SHIELDED DEVICES
  • 5.1. Obligations and responsibilities
  • 5.2. Steps to take when dealing with DU shields
• 6. SAFETY AND SECURITY CONSIDERATIONS FOR DU SHIELDED DEVICES
  • 6.1. Radiological Safety
  • 6.2. Safety and security for the storage of DU shielded devices
  • 6.3. Safety and security FOR THE transport of DU shielded devices
• 7. MANAGEMENT OPTIONS FOR DU
  • 7.1. General information
  • 7.2. Inventory information
  • 7.3. Management options for devices containing DU as shielding material
    • 7.3.1. Return to manufacturer/supplier
    • 7.3.2. Reuse or recycle
    • 7.3.3. Storage
    • 7.3.4. Disposal
• 8. CONCLUSIONS AND STEPS FORWARD
• Appendix I GENERAL ASPECTS OF RADIOACTIVE WASTE
• Appendix II CASE STUDY: DU SHIELDING CONTROL AND PROTECTION IN FRANCE
• Appendix III SPECIFIC REGULATORY REQUIREMENTS FOR STORAGE AND TRANSPORT OF DU IN HUNGARY
• REFERENCES
• CONTENTS OF THE ANNEXES NATIONAL REPORTS: EXAMPLES OF NATIONAL EXPERIENCES
• Annex I MEMBER STATE EXPERIENCE: AUSTRALIA
• Annex II MEMBER STATE EXPERIENCE: AZERBAIJAN
• Annex III MEMBER STATE EXPERIENCE: BULGARIA
• Annex IV MEMBER STATE EXPERIENCE: CANADA
• Annex V MEMBER STATE EXPERIENCE: CHILE
• Annex VI MEMBER STATE EXPERIENCE: FRANCE
• Annex VII MEMBER STATE EXPERIENCE: GEORGIA
• Annex VIII MEMBER STATE EXPERIENCE: HUNGARY
• Annex IX MEMBER STATE EXPERIENCE: INDONESIA
• Annex X MEMBER STATE EXPERIENCE: ISLAMIC REPUBLIC OF IRAN
• Annex XI MEMBER STATE EXPERIENCE: JORDAN
• Annex XII MEMBER STATE EXPERIENCE: KENYA
• Annex XIII MEMBER STATE EXPERIENCE: MADAGASCAR
• Annex XIV MEMBER STATE EXPERIENCE: MALAYSIA
• Annex XV MEMBER STATE EXPERIENCE: PAKISTAN
• Annex XVI MEMBER STATE EXPERIENCE: ROMANIA
• Annex XVII MEMBER STATE EXPERIENCE: SENEGAL
• Annex XVIII MEMBER STATE EXPERIENCE: SLOVAK REPUBLIC
• Annex XIX MEMBER STATE EXPERIENCE: SLOVENIA
• Annex XX MEMBER STATE EXPERIENCE: TAJIKISTAN
• Annex XXI MEMBER STATE EXPERIENCE: THAILAND
• Annex XXII MEMBER STATE EXPERIENCE: Türkiye
• Annex XXIII MEMBER STATE EXPERIENCE: UNITED STATES OF AMERICA
• Annex XXIV MEMBER STATE EXPERIENCE: VIET NAM
• GLOSSARY
• ABBREVIATIONS
• CONTRIBUTORS TO DRAFTING AND REVIEW
• STRUCTURE OF THE IAEA NUCLEAR ENERGY SERIES