Sustainability of Life Cycle Management for Nuclear Cementation-Based Technologies

1st Edition - May 25, 2021
Imprint: Woodhead Publishing
Editors: Rehab O. Abdel Rahman, Michael I. Ojovan
Language: English
Paperback ISBN:
9 7 8 - 0 - 1 2 - 8 1 8 3 2 8 - 1
eBook ISBN:
9 7 8 - 0 - 1 2 - 8 1 8 3 2 9 - 8

Sustainability of Life Cycle Management for Nuclear Cementation-Based Technologies, edited by Dr. Rahman and Dr. Ojovan, presents the latest knowledge and research on the managemen… Read more

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Sustainability of Life Cycle Management for Nuclear Cementation-Based Technologies, edited by Dr. Rahman and Dr. Ojovan, presents the latest knowledge and research on the management of cementitious systems within nuclear power plants. The book covers aging, development and updates on regulatory frameworks on a global scale, the development of cementitious systems for the immobilization of problematic wastes, and the decommissioning and decontamination of complex cementitious systems. The book's editors and their team of experts combine their practical knowledge to provide the reader with a thorough understanding on the sustainability of lifecycle management of cementitious systems within the nuclear industry.

Sections provide a comparative tool that presents national regulations concerning cementitious systems within nuclear power plants, check international and national evaluation results of the sustainability of different systems, help in the development of performance test procedures, and provide a guide on aging nuclear power plants and the long-term behavior of these systems in active and passive safety environments.

Cover image
Title page
Table of Contents
Copyright
Contributors
About the editors’
Preface
Part One: Cementitious systems in nuclear industry
1: Introduction to the nuclear industry sustainability
Abstract
1.1: Introduction
1.2: Introduction to material stability and radioactivity
1.3: Role of nuclear and isotopic technologies in supporting the sustainable development
1.4: Sustainability of the nuclear industry
1.5: Conclusion
2: Innovative and conventional cementitious systems in nuclear industry—Safety aspect
Abstract
2.1: Introduction
2.2: Nuclear reactors
2.3: Spent fuel storage facilities
2.4: Radioactive waste disposal facilities
2.5: ITER
2.6: Conclusion
3: Life cycle of nuclear cementitious structures, systems, and components
Abstract
3.1: Introduction
3.2: Preoperational phases for cement-based materials
3.3: Life cycle phases in the nuclear industry
3.4: Conclusion
Part Two: Behavior of nuclear cementitious systems and factors that affect its sustainability
4: Hydration process: Kinetics and thermodynamics
Abstract
4.1: Introduction
4.2: Alite hydration
4.3: Properties of hydrated Portland cement-based materials
4.4: Hydration of innovative cements
4.5: Conclusion
5: Long-term irradiation effects in cementitious systems
Abstract
5.1: Introduction
5.2: Application of cement-based materials in radioactive waste conditioning
5.3: Radiolysis effects
5.4: Gas evolution under radiolysis
5.5: Change in mechanical strength
5.6: Changes in microstructure
5.7: Changes in chemical durability
5.8: Modeling of the radiation processes in cement compounds
5.9: Conclusions
6: Sustainability of cementitious structures, systems, and components (SSC’s): Long-term environmental stressors
Abstract
6.1: Introduction
6.2: Effects of the ambient temperature on cementitious systems
6.3: Processes initiated by the presence of water
6.4: Durability of innovative cements
6.5: Codes and standards for durability design
6.6: Conclusion
7: Behavior of cementitious SSC’s in mitigating accidents
Abstract
7.1: Introduction
7.2: Saturated conditions in near surface disposal facilities
7.3: Dry spent fuel storage facility exposure to aircraft
7.4: Behavior of cementitious SSC’s in core meltdown accident
7.5: Conclusion
Part Three: Operation and maintenance of cementitious systems and its contribution to the sustainability
8: Considerations in construction of nuclear cements: Materials, technologies, and management systems
Abstract
8.1: Introduction
8.2: Cement-based materials for nuclear power plants
8.3: Conventional and advanced technologies in the construction of nuclear power plants
8.4: Lesson learned during the construction of new nuclear power plants
8.5: Conclusion
9: Innovative and conventional materials and designs of nuclear cementitious systems in radioactive waste management
Abstract
9.1: Fundamentals of cementing radioactive waste
9.2: Novel and conventional cement-based waste form
9.3: Technologies and procedures for preparing cementing liquid radioactive waste forms
9.4: Technologies and procedure for preparing cementing SRW forms
9.5: Unification of radioactive waste cementing processes
9.6: High-level radioactive waste cementing
9.7: Conclusions
10: Sustainability consideration during the design and construction of geological disposal
Abstract
Acknowledgment
10.1: Introduction
10.2: Overview of geological disposal concepts under study in Europe
10.3: Environmental condition studies of underground disposal
10.4: Alteration of cementitious materials
10.5: Durability of cementitious material in deep geological disposal
10.6: Concrete in the construction of engineered barriers for underground disposal facilities
10.7: Conclusion
11: Age management and maintenance of cementitious SSC’s during operation phase
Abstract
11.1: Introduction
11.2: Age management for cementitious SSC’s
11.3: Conditions assessment and maintenance of cementitious SSC’s
11.4: Conclusion
12: Techniques to test cementitious systems through their life cycles
Abstract
12.1: Introduction
12.2: Large-scale testing of cementitious SSC’s
12.3: Overview on nondestructive testing techniques for cementitious SSC’s
12.4: Application of testing techniques in nuclear facilities
12.5: Conclusion
Part Four: End of life cycle
13: Life cycle management of aged cementitious SSC's
Abstract
13.1: Introduction—Time span of nuclear concrete structures
13.2: The longevity problem
13.3: Concrete deterioration during a safe enclosure period
13.4: Weather enclosures
13.5: Structural assessment
13.6: Monitoring and maintenance
13.7: Radon emanation
13.8: Entombment
13.9: Case studies
13.10: Conclusions
14: Innovative and conventional decontamination techniques for cementitious structures
Abstract
14.1: Scope and objectives of concrete decontamination
14.2: Mechanical processes
14.3: Thermal processes
14.4: Chemical processes
14.5: Microbial processes
14.6: Special cementitious systems
14.7: Conclusions
15: Dismantling and demolition techniques for cementitious systems
Abstract
15.1: Scope and objectives of concrete dismantling and demolition
15.2: Mechanical cutting
15.3: Thermal cutting
15.4: Special cementitious systems
15.5: Advantages and disadvantages of dismantling/demolition techniques applicable to cementitious systems: A summary
15.6: Conclusions
16: Innovative and conventional techniques for managing the produced wastes
Abstract
16.1: Introduction
16.2: Concrete recycling from nuclear decommissioning
16.3: Recycling of inactive concrete
16.4: Operating experience at Connecticut Yankee NPP, United States, and other plants using similar strategies
16.5: Waste optimization from dismantling of biological shields
16.6: Conclusions
17: Case studies and lessons learned from decontamination, demolition, and managing the produced wastes
Abstract
18: Terms and glossary relevant to nuclear cementitious systems
Glossary
Index

Rehab O. Abdel Rahman

Dr. Rehab O. Abdel Rahman is professor of Chemical Nuclear Engineering at the Radioactive Waste Management Department, Hot Laboratories & Waste Management Center, Atomic Energy Authority of Egypt (AEAE). She received her Ph.D. degree in Nuclear Engineering and currently is safety assessment group leader. She participated in international projects and meetings on safety cases and safety assessments especially for disposal facilitates. Her widely published research focuses on radioactive waste management and decontamination. She supervises post graduate students, teaches undergraduate courses, and supports training activities within AEAE, serves as a member in international scientific committees. She is a managing editor for two international journals, (co)-editor of several books, contributed to the publication several book chapters, reviewer in several international journals, and frequent contributor on the topic of hazardous waste management. She awarded the State Encouragement Award in Engineering sciences , Egypt 2011

Affiliations and expertise

Associate Professor of Chemical Nuclear Engineering, Radioactive Waste Management Department, Hot Laboratories and Waste Management Center, Atomic Energy Authority of Egypt, Cairo, Egypt

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, UK

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