This report reviews and analyses experience in the application of different organizational and technological approaches to the management of waste containing C-14 and tritium, and reviews the different sources of such waste and the characteristics important in the selection of appropriate methods for its processing, storage, disposal and release.

Over the past decade significant progress has been achieved in the development of waste characterization and control procedures and equipment as a direct response to ever-increasing requirements for quality and reliability of information on waste characteristics. Failure in control procedures at any step can have important, adverse consequences and may result in producing waste packages which are not compliant with the waste acceptance criteria for disposal, thereby adversely impacting the repository. The information and guidance included in this publication corresponds to recent achievements and reflects the optimum approaches, thereby reducing the potential for error and enhancing the quality of the end product. -- Publisher's description.

This publication contains information on the dosimetry and monitoring of tritium, the use of protective clothing for work with tritium, safe practices in tritium handling laboratories and details of tritium compatible materials. The information has been compiled from experience in the various applications of tritium and should represent valuable source material to all users of tritium, including those involved in fusion R&D.

The classification of radioactive waste varies from state to state. This results in different management procedures for each country, while following IAEA and OECD/NEA recommendations. Radioactive waste comes from numerous sources. The largest volumes are generated by the decommissioning and dismantling of nuclear facilities. Long-lived, medium- and high-activity waste – categorized as the most hazardous types of waste – are in fact largely produced by nuclear power reactors, spent fuel reprocessing plants and nuclear accidents. Final disposal of very low-activity, low-activity and very short-lived waste is well controlled. However, final solutions for certain categories, including long-lived waste, sorted waste and spent graphite waste, are not yet in place. Management of Radioactive Waste reviews all the possible solutions and presents those chosen by the various states, including a chapter detailing policy on radioactive waste management, taking France as an example.

Radioactive waste management and contaminated site clean-up reviews radioactive waste management processes, technologies, and international experiences. Part one explores the fundamentals of radioactive waste including sources, characterisation, and processing strategies. International safety standards, risk assessment of radioactive wastes and remediation of contaminated sites and irradiated nuclear fuel management are also reviewed. Part two highlights the current international situation across Africa, Asia, Europe, and North America. The experience in Japan, with a specific chapter on Fukushima, is also covered. Finally, part three explores the clean-up of sites contaminated by weapons programmes including the USA and former USSR.Radioactive waste management and contaminated site clean-up is a comprehensive resource for professionals, researchers, scientists and academics in radioactive waste management, governmental and other regulatory bodies and the nuclear power industry. - Explores the fundamentals of radioactive waste including sources, characterisation, and processing strategies - Reviews international safety standards, risk assessment of radioactive wastes and remediation of contaminated sites and irradiated nuclear fuel management - Highlights the current international situation across Africa, Asia, Europe, and North America specifically including a chapter on the experience in Fukushima, Japan

Graphite is widely used in the nuclear industry and in research facilities and this has led to increasing amounts of irradiated graphite residing in temporary storage facilities pending disposal. This publication arises from a coordinated research project (CRP) on the processing of irradiated graphite to meet acceptance criteria for waste disposal.

Safety and environmental impact is of uppermost concern when dealing with the movement and storage of nuclear waste. The 20 chapters in 'An Introduction to Nuclear Waste Immobilisation' cover all important aspects of immobilisation, from nuclear decay, to regulations, to new technologies and methods. Significant focus is given to the analysis of the various matrices used in transport: cement, bitumen and glass, with the greatest attention being given to glass. The last chapter concentrates on the performance assessment of each matrix, and on new developments of ceramics and glass composite materials, thermochemical methods and in-situ metal matrix immobilisation. The book thoroughly covers all issues surrounding nuclear waste: from where to locate nuclear waste in the environment, through nuclear waste generation and sources, treatment schemes and technologies, immobilisation technologies and waste forms, disposal and long term behaviour. Particular attention is paid to internationally approved and worldwide-applied approaches and technologies.* Each chapter focuses on a different matrix used in nuclear waste immobilisation: Cement, bitumen, glass and new materials.* Keeps the most important issues surrounding nuclear waste – such as treatment schemes and technologies, and disposal - at the forefront.

Molten Salt Reactors and Thorium Energy, Second Edition is a fully updated comprehensive reference on the latest advances in MSR research and technology. Building on the successful first edition, Tom Dolan and the team of experts have fully updated the content to reflect the impressive advances from the last 5 years, ensuring this book continues to be the go-to reference on the topic. This new edition covers progress made in MSR design, details innovative experiments, and includes molten salt data, corrosion studies and deployment plans. The successful case studies section of the first edition have been removed, expanded, and fully updated, and are now published in a companion title called Global Case Studies on Molten Salt Reactors. Readers will gain a deep understanding of the advantages and challenges of MSR development and thorium fuel use, as well as step-by-step guidance on the latest in MSR reactor design. Each chapter provides a clear introduction, covers technical issues and includes examples and conclusions, while promoting the sustainability benefits throughout. - A fully updated comprehensive handbook on Molten Salt Reactors and Thorium Energy, written by a team of global experts - Covers MSR applications, technical issues, reactor types and reactor designs - Includes 3 brand new chapters which reflect the latest advances in research and technology since the first edition published - Presents case studies on molten salt reactors which aid in the transition to net zero by providing abundant clean, safe energy to complement wind and solar powe