Handbook of Advanced Radioactive Waste Conditioning Technologies

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

• Contributor contact detailsWoodhead Publishing Series in EnergyChapter 1: Radioactive waste characterization and selection of processing technologiesAbstract:1.1 Introduction1.2 Radioactive waste classification1.3 Radioactive waste characterization1.4 Radioactive waste processing1.5 Selection of conditioning technologies1.6 Sources of further information and advice1.7 AcknowledgementsPart I: Radioactive waste treatment processes and conditioning technologiesChapter 2: Compaction processes and technology for treatment and conditioning of radioactive wasteAbstract:2.1 Applicable waste streams in compaction processes and technology2.2 Compaction processes and technology2.3 End waste forms and quality control of compaction processes2.4 Pre-treatment in compaction processes2.5 Secondary wastes of compaction processes and technology2.6 Advantages and limitations of compaction processes and technoligy2.7 Future trends2.8 Sources of further information and adviceChapter 3: Incineration and plasma processes and technology for treatment and conditioning of radioactive wasteAbstract:3.1 Introduction3.2 Applicable waste streams in incineration processes and technology3.3 Incineration process and technology3.4 Plasma process and technology3.5 End waste form and quality control in incineration (plasma) processes3.6 Advantages and limitations of incineration (plasma) processes3.7 Future ternds3.8 Sources of further information and adviceChapter 4: Application of inorganic cements to the conditioning and immobilisation of radioactive wastesAbstract:4.1 Overview4.2 Manufacture of Portland cement4.3 Application of Portland cement4.4 Hydration of Portland cement4.5 Porosity and permeability4.6 Supplementary cementitious materials4.7 Mineral aggregates4.8 Service environments and cement performance in its service environment4.9 Standards and testing4.10 Organic materials added to Portland cement4.11 Service environments and lessons from historic concrete4.12 Non-Portland cement4.13 Immobilisation mechanisms4.14 Deterioration processes affecting Portland cement: processes and features4.15 Deterioration processes: carbonation4.16 Miscellaneous interactions of cement in its service environment4.17 Summary and conclusionsChapter 5: Calcination and vitrification processes for conditioning of radioactive wastesAbstract:5.1 Introduction5.2 Calcination and vitrification processes5.3 End waste forms and quality control in calcination and vitrification processes5.4 Future trendsChapter 6: Historical development of glass and ceramic waste forms for high level radioactive wastesAbstract:6.1 Introduction6.2 Borosilicate glass development in the United States6.3 Borosilicate glass development in France6.4 Borosilicate glass development in the United Kingdom6.5 Aluminosilicate glass development in Canada6.6 Phosphate glass development in the United States, Russia, Germany and Belgium6.7 Ceramic waste form development in various countriesChapter 7: Decommissioning of nuclear facilities and environmental remediation: generation and management of radioactive and other wastesAbstract:7.1 Introduction7.2 What is decommissioning?7.3 Generation of decommissioning waste7.4 Waste from dismantling of nuclear facilities7.5 Waste from decontamination for decommissioning purposes7.6 Problematic decommissioning waste7.7 Environmental remediation as a decommissioning component7.8 Future trendsPart II: Advanced materials and technologies for the immobilisation of radioactive wastesChapter 8: Development of geopolymers for nuclear waste immobilisationAbstract:8.1 Nuclear wastes around the world8.2 Cementitious low-level waste (LLW)/intermediate-level waste (ILW) waste forms8.3 Future work8.4 Conclusions8.5 Sources of further information and advice8.6 AcknowledgementsChapter 9: Development of glass matrices for high level radioactive wastesAbstract:9.1 Introduction9.2 High level radioactive waste (HLW) glass processing9.3 Glass formulation and waste loading9.4 Glass quality: feed-forward process control9.5 Other glasses9.6 Future trends9.7 Sources of further information and adviceChapter 10: Development of ceramic matrices for high level radioactive wastesAbstract:10.1 Introduction10.2 Ceramic phases10.3 Ceramic waste forms for the future10.5 AcknowledgementChapter 11: Development of waste packages for the disposal of radioactive waste: French experienceAbstract:11.1 Introduction11.2 Existing waste packages used for the disposal of short-lived low- and intermediate-level waste11.3 Waste packages being developed for other types of radioactive waste11.4 Future trends11.5 Sources of further information and advice11.6 Glossary of termsChapter 12: Development and use of metal containers for the disposal of radioactive wastesAbstract:12.1 Introduction12.2 Safety in radioactive waste disposal12.3 Approaches to physical containment of radioactive waste12.4 Metal corrosion: an overview12.5 Radioactive waste containers in use or proposed12.6 Quality management of metal containers12.7 Future trends12.8 Sources of further information and advicePart III: Radioactive waste long-term performance assessment and knowledge management techniquesChapter 13: Failure mechanisms of high level nuclear waste forms in storage and geological disposal conditionsAbstract:13.1 Introduction: the main aspects of the back-end of the nuclear fuel cycle13.2 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 water13.4 Future trendsChapter 14: Development of long-term behavior models for radioactive waste formsAbstract:14.1 Introduction14.2 Thermo-hydro-mechanical performance modeling14.3 Corrosion modeling14.4 Source term release modeling14.5 Future trendsChapter 15: Knowledge management for radioactive waste management organisationsAbstract:15.1 Introduction15.2 Challenges for managing nuclear knowledge in radioactive waste management organisations15.3 Managing nuclear knowledge over very long timescales15.4 Implementing knowledge management in radioactive waste management organisations15.5 Knowledge management tools and techniques for use in radioactive waste management15.6 ConclusionsIndex