Handbook of advanced radioactive waste conditioning technologies

書誌事項

Handbook of advanced radioactive waste conditioning technologies

edited by Michael I. Ojovan

(Woodhead Publishing series in energy, 12)

Woodhead, 2011

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注記

Includes bibliographical references and index

内容説明・目次

内容説明

Radioactive wastes are generated from a wide range of sources, including the power industry, and medical and scientific research institutions, presenting a range of challenges in dealing with a diverse set of radionuclides of varying concentrations. Conditioning technologies are essential for the encapsulation and immobilisation of these radioactive wastes, forming the initial engineered barrier required for their transportation, storage and disposal. The need to ensure the long term performance of radioactive waste forms is a key driver of the development of advanced conditioning technologies. The Handbook of advanced radioactive waste conditioning technologies provides a comprehensive and systematic reference on the various options available and under development for the treatment and immobilisation of radioactive wastes. The book opens with an introductory chapter on radioactive waste characterisation and selection of conditioning technologies. Part one reviews the main radioactive waste treatment processes and conditioning technologies, including volume reduction techniques such as compaction, incineration and plasma treatment, as well as encapsulation methods such as cementation, calcination and vitrification. This coverage is extended in part two, with in-depth reviews of the development of advanced materials for radioactive waste conditioning, including geopolymers, glass and ceramic matrices for nuclear waste immobilisation, and waste packages and containers for disposal. Finally, part three reviews the long-term performance assessment and knowledge management techniques applicable to both spent nuclear fuels and solid radioactive waste forms. With its distinguished international team of contributors, the Handbook of advanced radioactive waste conditioning technologies is a standard reference for all radioactive waste management professionals, radiochemists, academics and researchers involved in the development of the nuclear fuel cycle.

目次

Contributor contact details 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

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詳細情報

  • NII書誌ID(NCID)
    BB08572927
  • ISBN
    • 9781845696269
  • 出版国コード
    uk
  • タイトル言語コード
    eng
  • 本文言語コード
    eng
  • 出版地
    Cambridge [England]
  • ページ数/冊数
    xv, 488 p.
  • 大きさ
    25 cm
  • 分類
  • 件名
  • 親書誌ID
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