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.

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.

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.

This book discusses the history of nuclear decommissioning as a science and industry. It explores the early, little-known period when the term “decommissioning” was not used in the nuclear context and the end-of-life operations of a nuclear facility were a low priority. It then describes the subsequent period when decommissioning was recognized as a separate phase of the nuclear lifecycle, before bringing readers up to date with today’s state of the art. The author addresses decommissioning as a mature industry in an era in which large, commercial nuclear reactors and other fuel-cycle installations have been fully dismantled, and their sites returned to other uses. The book also looks at the birth, growth and maturity of decommissioning, focusing on how new issues emerged, how these were gradually addressed, and the lessons learned from them. Further, it examines the technologies and management advances in science and industry that followed these solutions. Nuclear Decommissioning is a point of reference for industry researchers and decommissioning practitioners looking to enrich their knowledge of decommissioning in recent decades as well as the modern industry. The book is also of interest to historians and students who wish to learn more about the history of nuclear decommissioning.

Graphite has been used as a moderator and reflector of neutrons in more than 100nuclear power plants and in many research and plutonium-production reactors. It is usedprimarily as a neutron reflector or neutron moderator, although graphite is also used for other features of reactor cores, such as fuel sleeves. Many of the graphite-moderated reactors are now quite old, with some already shutdown. Therefore radioactive graphite dismantling and the management of radioactive graphite waste are becoming an increasingly important issue for a number of IAEA Member States. This report provides a comprehensive discussion of radioactive graphite waste characterization, handling, conditioning and disposal throughout the operating and decommissioning life cycle.

Operating at a high level of fuel efficiency, safety, proliferation-resistance, sustainability and cost, generation IV nuclear reactors promise enhanced features to an energy resource which is already seen as an outstanding source of reliable base load power. The performance and reliability of materials when subjected to the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors are essential areas of study, as key considerations for the successful development of generation IV reactors are suitable structural materials for both in-core and out-of-core applications. Structural Materials for Generation IV Nuclear Reactors explores the current state-of-the art in these areas. Part One reviews the materials, requirements and challenges in generation IV systems. Part Two presents the core materials with chapters on irradiation resistant austenitic steels, ODS/FM steels and refractory metals amongst others. Part Three looks at out-of-core materials. Structural Materials for Generation IV Nuclear Reactors is an essential reference text for professional scientists, engineers and postgraduate researchers involved in the development of generation IV nuclear reactors. Introduces the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors and implications for structural materials Contains chapters on the key core and out-of-core materials, from steels to advanced micro-laminates Written by an expert in that particular area