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Woodhead Publishing Series in Energy
Chapter 1: Radioactive waste characterization and selection of
processing technologies
Abstract:
1.1 Introduction
1.2 Radioactive waste classification
1.3 Radioactive waste characterization
1.4 Radioactive waste processing
1.5 Selection of conditioning technologies
1.6 Sources of further information and advice
1.7 Acknowledgements
Part I: Radioactive waste treatment processes and conditioning
technologies
Chapter 2: Compaction processes and technology for treatment and
conditioning of radioactive waste
Abstract:
2.1 Applicable waste streams in compaction processes and
technology
2.2 Compaction processes and technology
2.3 End waste forms and quality control of compaction processes
2.4 Pre-treatment in compaction processes
2.5 Secondary wastes of compaction processes and technology
2.6 Advantages and limitations of compaction processes and
technoligy
2.7 Future trends
2.8 Sources of further information and advice
Chapter 3: Incineration and plasma processes and technology for
treatment and conditioning of radioactive waste
Abstract:
3.1 Introduction
3.2 Applicable waste streams in incineration processes and
technology
3.3 Incineration process and technology
3.4 Plasma process and technology
3.5 End waste form and quality control in incineration (plasma)
processes
3.6 Advantages and limitations of incineration (plasma)
processes
3.7 Future ternds
3.8 Sources of further information and advice
Chapter 4: Application of inorganic cements to the conditioning and
immobilisation of radioactive wastes
Abstract:
4.1 Overview
4.2 Manufacture of Portland cement
4.3 Application of Portland cement
4.4 Hydration of Portland cement
4.5 Porosity and permeability
4.6 Supplementary cementitious materials
4.7 Mineral aggregates
4.8 Service environments and cement performance in its service
environment
4.9 Standards and testing
4.10 Organic materials added to Portland cement
4.11 Service environments and lessons from historic concrete
4.12 Non-Portland cement
4.13 Immobilisation mechanisms
4.14 Deterioration processes affecting Portland cement: processes
and features
4.15 Deterioration processes: carbonation
4.16 Miscellaneous interactions of cement in its service
environment
4.17 Summary and conclusions
Chapter 5: Calcination and vitrification processes for conditioning
of radioactive wastes
Abstract:
5.1 Introduction
5.2 Calcination and vitrification processes
5.3 End waste forms and quality control in calcination and
vitrification processes
5.4 Future trends
Chapter 6: Historical development of glass and ceramic waste forms
for high level radioactive wastes
Abstract:
6.1 Introduction
6.2 Borosilicate glass development in the United States
6.3 Borosilicate glass development in France
6.4 Borosilicate glass development in the United Kingdom
6.5 Aluminosilicate glass development in Canada
6.6 Phosphate glass development in the United States, Russia,
Germany and Belgium
6.7 Ceramic waste form development in various countries
Chapter 7: Decommissioning of nuclear facilities and environmental
remediation: generation and management of radioactive and other
wastes
Abstract:
7.1 Introduction
7.2 What is decommissioning?
7.3 Generation of decommissioning waste
7.4 Waste from dismantling of nuclear facilities
7.5 Waste from decontamination for decommissioning purposes
7.6 Problematic decommissioning waste
7.7 Environmental remediation as a decommissioning component
7.8 Future trends
Part II: Advanced materials and technologies for the immobilisation
of radioactive wastes
Chapter 8: Development of geopolymers for nuclear waste
immobilisation
Abstract:
8.1 Nuclear wastes around the world
8.2 Cementitious low-level waste (LLW)/intermediate-level waste
(ILW) waste forms
8.3 Future work
8.4 Conclusions
8.5 Sources of further information and advice
8.6 Acknowledgements
Chapter 9: Development of glass matrices for high level radioactive
wastes
Abstract:
9.1 Introduction
9.2 High level radioactive waste (HLW) glass processing
9.3 Glass formulation and waste loading
9.4 Glass quality: feed-forward process control
9.5 Other glasses
9.6 Future trends
9.7 Sources of further information and advice
Chapter 10: Development of ceramic matrices for high level
radioactive wastes
Abstract:
10.1 Introduction
10.2 Ceramic phases
10.3 Ceramic waste forms for the future
10.5 Acknowledgement
Chapter 11: Development of waste packages for the disposal of
radioactive waste: French experience
Abstract:
11.1 Introduction
11.2 Existing waste packages used for the disposal of short-lived
low- and intermediate-level waste
11.3 Waste packages being developed for other types of radioactive
waste
11.4 Future trends
11.5 Sources of further information and advice
11.6 Glossary of terms
Chapter 12: Development and use of metal containers for the
disposal of radioactive wastes
Abstract:
12.1 Introduction
12.2 Safety in radioactive waste disposal
12.3 Approaches to physical containment of radioactive waste
12.4 Metal corrosion: an overview
12.5 Radioactive waste containers in use or proposed
12.6 Quality management of metal containers
12.7 Future trends
12.8 Sources of further information and advice
Part III: Radioactive waste long-term performance assessment and
knowledge management techniques
Chapter 13: Failure mechanisms of high level nuclear waste forms in
storage and geological disposal conditions
Abstract:
13.1 Introduction: the main aspects of the back-end of the nuclear
fuel cycle
13.2 Effects of radiation on properties relevant for storage and
disposal of high level waste (HLW)
13.3 Chemical corrosion of high level waste (HLW) in presence of
water
13.4 Future trends
Chapter 14: Development of long-term behavior models for
radioactive waste forms
Abstract:
14.1 Introduction
14.2 Thermo-hydro-mechanical performance modeling
14.3 Corrosion modeling
14.4 Source term release modeling
14.5 Future trends
Chapter 15: Knowledge management for radioactive waste management
organisations
Abstract:
15.1 Introduction
15.2 Challenges for managing nuclear knowledge in radioactive waste
management organisations
15.3 Managing nuclear knowledge over very long timescales
15.4 Implementing knowledge management in radioactive waste
management organisations
15.5 Knowledge management tools and techniques for use in
radioactive waste management
15.6 Conclusions
Index
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.
"A comprehensive and valuable reference book written by a team of
outstanding experts, dealing with one of the most critical aspects
of nuclear power generation: the safe and sound management of the
radioactive waste." --Dr Rudolf Burcl, European Commission, JRC -
Institute for Energy, Petten, The Netherlands
"Woodhead Publishing has commissioned recognized world experts in
reporting on the latest radioactive waste conditioning technologies
for this valuable new book." --Gary A. Benda, Deputy Managing
Director and Chairman, Program Advisory Committee, WM Symposia, USA
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