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An Introduction to Nuclear Waste Immobilisation
1st Edition - September 19, 2005
Authors: Michael I. Ojovan, William E Lee, William E. Lee
eBook ISBN:
9 7 8 - 0 - 0 8 - 0 4 5 5 7 1 - 6
Safety and environmental impact is of uppermost concern when dealing with the movement and storage of nuclear waste. The 20 chapters in 'An Introduction to Nuclear Waste… Read more
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Safety and environmental impact is of uppermost concern when dealing with the movement and storage of nuclear waste. The 20 chapters in 'An Introduction to Nuclear Waste Immobilisation' cover all important aspects of immobilisation, from nuclear decay, to regulations, to new technologies and methods. Significant focus is given to the analysis of the various matrices used in transport: cement, bitumen and glass, with the greatest attention being given to glass. The last chapter concentrates on the performance assessment of each matrix, and on new developments of ceramics and glass composite materials, thermochemical methods and in-situ metal matrix immobilisation. The book thoroughly covers all issues surrounding nuclear waste: from where to locate nuclear waste in the environment, through nuclear waste generation and sources, treatment schemes and technologies, immobilisation technologies and waste forms, disposal and long term behaviour. Particular attention is paid to internationally approved and worldwide-applied approaches and technologies.
* Each chapter focuses on a different matrix used in nuclear waste immobilisation: Cement, bitumen, glass and new materials.
* Keeps the most important issues surrounding nuclear waste – such as treatment schemes and technologies, and disposal - at the forefront.
* Keeps the most important issues surrounding nuclear waste – such as treatment schemes and technologies, and disposal - at the forefront.
1. Introduction to immobilisation
1.1 Introduction
1.2 The importance of waste
1.3 Radioactive waste
1.4 Recycling
1.5 Waste minimisation
1.6 Immobilisation
1.7 Time frames
1.8 Bibliography
2. Nuclear decay
2.1. Nuclear decay
2.2. Decay law
2.3. Radioactive equilibrium
2.4. Activity
2.5. Alpha decay
2.6. Beta decay
2.7. Gamma decay
2.8. Spontaneous fission
2.9. Radionuclide characteristics
2.10. Bibliography
3. Contaminants and hazards
3.1. Elemental abundance
3.2. Migration and redistribution
3.3. Hazard potential
3.4. Relative hazard
3.5. Real hazard concept
3.6. Form factors that diminish hazard
3.7. Bibliography
4. Heavy metals
4.1. Metallic contaminants
4.2. Biogeochemical cycle
4.3. Heavy metals
4.4. Heavy metals in living species
4.5. Lead
4.6. Mercury
4.7. Cadmium
4.8. Arsenic
4.9. Bibliography
5. Naturally occurring radionuclides
5.1. NORM and TENORM
5.2. Primordial radionuclides
5.3. Cosmogenic radionuclides
5.4. Natural radionuclides in igneous rocks
5.5. Natural radionuclides in sedimentary rocks and soils
5.6. Natural radionuclides in sea water
5.7. Radon emissions
5.8. Natural radionuclides in the human body
5.9. Bibliography
6. Background radiation
6.1. Radiation is natural
6.2. Dose units
6.3. Biological consequences of irradiation
6.4. Background radiation
6.5. Bibliography
7. Nuclear waste regulations
7.1. Regulatory organisations
7.2. Protection philosophies
7.3. Regulation of radioactive materials and sources
7.4. Exemption criteria and levels
7.5. Clearance of materials from regulatory control
7.6. Double standards
7.7. Dose limits
7.8. Control of radiation hazards
7.9. Bibliography
8. Principles of nuclear waste management
8.1. International consensus
8.2. Objective of radioactive waste management
8.3. Fundamental principles
8.4. Comments on the fundamental principles
8.5. Ethical principles
8.6. Joint convention
8.7. Bibliography
9. Sources and characteristics of nuclear waste
9.1. Key waste characteristics
9.2. Classification schemes
9.3. Examples of waste classification
9.4. Sources of waste
9.5. Front end and operational NFC waste
9.6. Back end Open NFC waste
9.7. Back end Closed NFC waste
9.8. Back end NFC decommissioning waste
9.9. Non-NFC wastes
9.10. Accidental wastes
9.11. Bibliography
10. Short-lived waste radionuclides
10.1. Introduction
10.2. Tritium
10.3. Cobalt-60
10.4. Strontium-90
10.5. Caesium-137
10.6. Bibliography
11. Long-lived waste radionuclides
11.1. Introduction
11.2. Carbon-14
11.3. Technetium-99
11.4. Iodine-129
11.5. Plutonium
11.6. Neptunium-237
11.7. Criticality
11.8. Bibliography
12. Management and characterisation of radioactive waste
12.1. Management roadmaps
12.2. Predisposal
12.3. Disposal
12.4. Characterisation
12.5. Bibliography
13. Pre-treatment of radioactive wastes
13.1. Pre-treatment definition
13.2. Collection and segregation
13.3. Adjustment
13.4. Size reduction
13.5. Packaging
13.6. Decontamination
13.7. Bibliography
14. Treatment of radioactive wastes
14.1. Treatment objectives
14.2. Treatment of aqueous waste
14.3. Treatment of organic liquid wastes
14.4. Treatment of solid wastes
14.5. Treatment of gaseous and airborne effluents
14.6. Partitioning and transmutation
14.7. Bibliography
15. Immobilisation of radioactive wastes in cement
15.1. Waste immobilisation
15.2. Wasteform leaching behaviour
15.3. Immobilisation techniques
15.4. Immobilisation in hydraulic cements
15.5. Hydraulic cements
15.6. Cement hydration
15.7. Hydrated cement composition
15.8. Cementation of radioactive wastes
15.9. Modified and composite cement systems
15.10. Cementation technology
15.11. Acceptance criteria
15.12. Bibliography
16. Immobilisation of radioactive wastes in bitumen
16.1. Bituminisation
16.2. Composition and properties of bitumen
16.3. Bituminous materials for waste immobilisation
16.4. Bituminisation technique
16.5. Acceptance criteria
16.6. Bitumen versus cement
16.7. Bibliography
17. Immobilisation of radioactive wastes in glass
17.1. Vitrification
17.2. Immobilisation mechanisms
17.3. Retention of radionuclides
17.4. Nuclear waste glasses
17.5. Nuclear waste glass compositions
17.6. Borosilicate glasses
17.7. Role of boron oxide
17.8. Role of intermediates and modifiers
17.9. Difficult elements
17.10. Phosphate glasses
17.11. Glass composites
17.12. Vitrification processes
17.13. Cold crucible melters
17.14. Vitrification technology
17.15. Calcination
17.16. Radionuclide volatility
17.18. Acceptance criteria
17.19. Bibliography
18. New immobilising hosts and technologies
18.1. New approaches
18.2. Crystalline wasteforms
18.3. Polyphase crystalline wasteforms: Synroc
18.4. Polyphase crystalline waste forms: composites
18.5. New technological approaches
18.6. Metal matrix immobilisation
18.7. Bibliography
19. Nuclear waste disposal
19.1. Disposal/Storage concepts
19.2. Retention times
19.3. Multibarrier concept
19.4. Disposal/Storage options
19.5. Role of the EBS
19.6. Importance of geology
19.7. Transport of radionuclides
19.8. Disposal/Storage experience
19.9. Acceptance criteria
19.10. Bibliography
20. Performance assessment
20.1. Safety and performance assessments
20.2. Safety requirements
20.3. Safety case content
20.4. Cement performance
20.5. Bitumen performance
20.6. Glass performance
20.7. Radiation effects
20.8. Research laboratories
20.9. Conclusion
20.10. Bibliography
1.1 Introduction
1.2 The importance of waste
1.3 Radioactive waste
1.4 Recycling
1.5 Waste minimisation
1.6 Immobilisation
1.7 Time frames
1.8 Bibliography
2. Nuclear decay
2.1. Nuclear decay
2.2. Decay law
2.3. Radioactive equilibrium
2.4. Activity
2.5. Alpha decay
2.6. Beta decay
2.7. Gamma decay
2.8. Spontaneous fission
2.9. Radionuclide characteristics
2.10. Bibliography
3. Contaminants and hazards
3.1. Elemental abundance
3.2. Migration and redistribution
3.3. Hazard potential
3.4. Relative hazard
3.5. Real hazard concept
3.6. Form factors that diminish hazard
3.7. Bibliography
4. Heavy metals
4.1. Metallic contaminants
4.2. Biogeochemical cycle
4.3. Heavy metals
4.4. Heavy metals in living species
4.5. Lead
4.6. Mercury
4.7. Cadmium
4.8. Arsenic
4.9. Bibliography
5. Naturally occurring radionuclides
5.1. NORM and TENORM
5.2. Primordial radionuclides
5.3. Cosmogenic radionuclides
5.4. Natural radionuclides in igneous rocks
5.5. Natural radionuclides in sedimentary rocks and soils
5.6. Natural radionuclides in sea water
5.7. Radon emissions
5.8. Natural radionuclides in the human body
5.9. Bibliography
6. Background radiation
6.1. Radiation is natural
6.2. Dose units
6.3. Biological consequences of irradiation
6.4. Background radiation
6.5. Bibliography
7. Nuclear waste regulations
7.1. Regulatory organisations
7.2. Protection philosophies
7.3. Regulation of radioactive materials and sources
7.4. Exemption criteria and levels
7.5. Clearance of materials from regulatory control
7.6. Double standards
7.7. Dose limits
7.8. Control of radiation hazards
7.9. Bibliography
8. Principles of nuclear waste management
8.1. International consensus
8.2. Objective of radioactive waste management
8.3. Fundamental principles
8.4. Comments on the fundamental principles
8.5. Ethical principles
8.6. Joint convention
8.7. Bibliography
9. Sources and characteristics of nuclear waste
9.1. Key waste characteristics
9.2. Classification schemes
9.3. Examples of waste classification
9.4. Sources of waste
9.5. Front end and operational NFC waste
9.6. Back end Open NFC waste
9.7. Back end Closed NFC waste
9.8. Back end NFC decommissioning waste
9.9. Non-NFC wastes
9.10. Accidental wastes
9.11. Bibliography
10. Short-lived waste radionuclides
10.1. Introduction
10.2. Tritium
10.3. Cobalt-60
10.4. Strontium-90
10.5. Caesium-137
10.6. Bibliography
11. Long-lived waste radionuclides
11.1. Introduction
11.2. Carbon-14
11.3. Technetium-99
11.4. Iodine-129
11.5. Plutonium
11.6. Neptunium-237
11.7. Criticality
11.8. Bibliography
12. Management and characterisation of radioactive waste
12.1. Management roadmaps
12.2. Predisposal
12.3. Disposal
12.4. Characterisation
12.5. Bibliography
13. Pre-treatment of radioactive wastes
13.1. Pre-treatment definition
13.2. Collection and segregation
13.3. Adjustment
13.4. Size reduction
13.5. Packaging
13.6. Decontamination
13.7. Bibliography
14. Treatment of radioactive wastes
14.1. Treatment objectives
14.2. Treatment of aqueous waste
14.3. Treatment of organic liquid wastes
14.4. Treatment of solid wastes
14.5. Treatment of gaseous and airborne effluents
14.6. Partitioning and transmutation
14.7. Bibliography
15. Immobilisation of radioactive wastes in cement
15.1. Waste immobilisation
15.2. Wasteform leaching behaviour
15.3. Immobilisation techniques
15.4. Immobilisation in hydraulic cements
15.5. Hydraulic cements
15.6. Cement hydration
15.7. Hydrated cement composition
15.8. Cementation of radioactive wastes
15.9. Modified and composite cement systems
15.10. Cementation technology
15.11. Acceptance criteria
15.12. Bibliography
16. Immobilisation of radioactive wastes in bitumen
16.1. Bituminisation
16.2. Composition and properties of bitumen
16.3. Bituminous materials for waste immobilisation
16.4. Bituminisation technique
16.5. Acceptance criteria
16.6. Bitumen versus cement
16.7. Bibliography
17. Immobilisation of radioactive wastes in glass
17.1. Vitrification
17.2. Immobilisation mechanisms
17.3. Retention of radionuclides
17.4. Nuclear waste glasses
17.5. Nuclear waste glass compositions
17.6. Borosilicate glasses
17.7. Role of boron oxide
17.8. Role of intermediates and modifiers
17.9. Difficult elements
17.10. Phosphate glasses
17.11. Glass composites
17.12. Vitrification processes
17.13. Cold crucible melters
17.14. Vitrification technology
17.15. Calcination
17.16. Radionuclide volatility
17.18. Acceptance criteria
17.19. Bibliography
18. New immobilising hosts and technologies
18.1. New approaches
18.2. Crystalline wasteforms
18.3. Polyphase crystalline wasteforms: Synroc
18.4. Polyphase crystalline waste forms: composites
18.5. New technological approaches
18.6. Metal matrix immobilisation
18.7. Bibliography
19. Nuclear waste disposal
19.1. Disposal/Storage concepts
19.2. Retention times
19.3. Multibarrier concept
19.4. Disposal/Storage options
19.5. Role of the EBS
19.6. Importance of geology
19.7. Transport of radionuclides
19.8. Disposal/Storage experience
19.9. Acceptance criteria
19.10. Bibliography
20. Performance assessment
20.1. Safety and performance assessments
20.2. Safety requirements
20.3. Safety case content
20.4. Cement performance
20.5. Bitumen performance
20.6. Glass performance
20.7. Radiation effects
20.8. Research laboratories
20.9. Conclusion
20.10. Bibliography
- No. of pages: 250
- Language: English
- Published: September 19, 2005
- Imprint: Elsevier Science
- eBook ISBN: 9780080455716
MO
Michael I. Ojovan
Michael I. Ojovan has been Nuclear Engineer of International Atomic Energy Agency (IAEA), visiting Professor of Imperial College London, Associate Reader in Materials Science and Waste Immobilisation of the University of Sheffield, UK, and Leading Scientist of Radiochemistry Department of Lomonosov Moscow State University. M. Ojovan is Editorial Board Member of scientific journals: “Materials Degradation” (Nature Partner Journal), “International Journal of Corrosion”, “Science and Technology of Nuclear Installations”, “Journal of Nuclear Materials”, and Associate Editor of journal “Innovations in Corrosion and Materials Science”. He has published 12 monographs including the “Handbook of Advanced Radioactive Waste Conditioning Technologies” by Woodhead and three editions of “An Introduction to Nuclear Waste Immobilisation” by Elsevier – 2005, 2013 and 2019. He has founded and led the IAEA International Predisposal Network (IPN) and the IAEA International Project on Irradiated Graphite Processing (GRAPA). M. Ojovan is known for the connectivity-percolation theory of glass transition, Sheffield model (two-exponential equation) of viscosity of glasses and melts, condensed Rydberg matter, metallic and glass-composite materials for nuclear waste immobilisation, and self-sinking capsules to investigate Earth’ deep interior.
Affiliations and expertise
Department of Materials Science and Engineering, University of Sheffield, UKWL
William E Lee
Professor William E. Lee FREng is Deputy Chair of the Government advisory Committee on Radioactive Waste Management (CoRWM), and Director of the Centre for Nuclear Engineering at Imperial College London, UK.
Affiliations and expertise
Immobilisation Science Laboratory, University of Sheffield, UK.WL
William E. Lee
Professor Lee has been Co-Director of the Institute of Security Science and Technology (ISST), Chair in Ceramic Science and Engineering, and President of the American Ceramic Society. Previous positions at Imperial include Director of the Centre for Nuclear Engineering, Director of the Centre for Doctoral Training in Nuclear Energy (with Cambridge and The Open Universities), and Director of the Centre for Advanced Structural Ceramics. He is a member of the Government advisory committee The Nuclear Innovation and Research Advisory Board (NIRAB), the Leverhulme Trust Panel of Advisors, the Royal Academy of Engineering International Activities Committee, and the Scientific and Environmental Advisory Board Tokamak Energy Ltd. He was from Jan 2006 to Sept 2010 Head of the Department of Materials. Bill was Deputy Chair of the Government advisory Committee on Radioactive Waste Management (CoRWM) from 2007-2013, has acted as special advisor nuclear to the House of Lords Science and Technology Committee (2013) and is an IAEA Technical Expert.
Affiliations and expertise
Department of Materials, Imperial College London, UK