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Informationen zum Autor 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.
List of contents
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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 Futu
Report
"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
