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The implementation of advanced nuclear systems requires that new technologies associated with the back end of the fuel cycle are developed. The separation of minor actinides from other fuel components is one of the advanced concepts being studied to help close the nuclear fuel cycle and to improve the long-term effects on the performance of geological repositories. Separating spent fuel elements and subsequently converting them through transmutation into short-lived nuclides should considerably reduce the longterm risks associated with nuclear power generation. R&D programmes worldwide are attempting to address such challenges, and many processes for advanced reprocessing and partitioning minor actinides are being developed. This report provides a comprehensive overview of progress on separation chemistry processes, and in particular on the technologies associated with the separation and recovery of minor actinides for recycling so as to help move towards the implementation of advanced fuel cycles. The report examines both aqueous and pyro processes, as well as the status of current and proposed technologies described according to the hierarchy of separations targeting different fuel components. The process criteria that will affect technology downselection are also reviewed, as are non-proliferation requirements. The maturity of different reprocessing techniques are assessed using a scale based on the technology readiness level, and perspectives for future R&D are reviewed.
The implementation of advanced nuclear systems requires that new technologies associated with the back end of the fuel cycle are developed. The separation of minor actinides from other fuel components is one of the advanced concepts being studied to help close the nuclear fuel cycle and to improve the long-term effects on the performance of geological repositories. Separating spent fuel elements and subsequently converting them through transmutation into short-lived nuclides should considerably reduce the longterm risks associated with nuclear power generation.
"In this analysis we have presented a method that provides insight into future fuel cycle alternatives by clarifying the complexity of choosing an appropriate fuel cycle in the context of the distribution of burdens and benefits between generations. The current nuclear power deployment practices, together with three future fuel cycles were assessed."--Page 227.
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
PROMISING NEW APPROACHES TO RECYCLE CARBON DIOXIDE AND REDUCE EMISSIONS With this book as their guide, readers will learn a variety of new approaches and methods to recycle and reuse carbon dioxide (CO2) in order to produce green fuels and chemicals and, at the same time, minimize CO2 emissions. The authors demonstrate how to convert CO2 into a broad range of essential products by using alternative green energy sources, such as solar, wind, and hydro-power as well as sustainable energy sources. Readers will discover that CO2 can be a driving force for the sustainable future of both the chemical industry and the energy and fuels industry. Green Carbon Dioxide features a team of expert authors, offering perspectives on the latest breakthroughs in CO2 recycling from Asia, Europe, and North America. The book begins with an introduction to the production of CO2-based fuels and chemicals. Next, it covers such topics as: Transformation of CO2 to useable products through free-radical-induced reactions Hydrogenation of CO2 to liquid fuels Direct synthesis of organic carbonates from CO2 and alcohols using heterogeneous oxide catalysts Electrocatalytic reduction of CO2 in methanol medium Fuel production from photocatalytic reduction of CO2 with water using TiO2-based nanocomposites Use of CO2 in enhanced oil recovery and carbon capture and sequestration More than 1,000 references enable readers to explore individual topics in greater depth. Green Carbon Dioxide offers engineers, chemists, and managers in the chemical and energy and fuel industries a remarkable new perspective, demonstrating how CO2 can play a significant role in the development of a sustainable Earth.
Originally published in 1983, this book presents both the technical and political information necessary to evaluate the emerging threat to world security posed by recent advances in uranium enrichment technology. Uranium enrichment has played a relatively quiet but important role in the history of efforts by a number of nations to acquire nuclear weapons and by a number of others to prevent the proliferation of nuclear weapons. For many years the uranium enrichment industry was dominated by a single method, gaseous diffusion, which was technically complex, extremely capital-intensive, and highly inefficient in its use of energy. As long as this remained true, only the richest and most technically advanced nations could afford to pursue the enrichment route to weapon acquisition. But during the 1970s this situation changed dramatically. Several new and far more accessible enrichment techniques were developed, stimulated largely by the anticipation of a rapidly growing demand for enrichment services by the world-wide nuclear power industry. This proliferation of new techniques, coupled with the subsequent contraction of the commercial market for enriched uranium, has created a situation in which uranium enrichment technology might well become the most important contributor to further nuclear weapon proliferation. Some of the issues addressed in this book are: A technical analysis of the most important enrichment techniques in a form that is relevant to analysis of proliferation risks; A detailed projection of the world demand for uranium enrichment services; A summary and critique of present institutional non-proliferation arrangements in the world enrichment industry, and An identification of the states most likely to pursue the enrichment route to acquisition of nuclear weapons.
Nuclear Waste Management Facilities: Advances, Environmental Impacts, and Future Prospects examines best practices and recent trends in improving nuclear safety and reducing the negative environmental impacts of nuclear waste. With strong emphasis on regulatory requirements, this reference is essential for designing new integrated waste management practices, using lessons learned from historical and current practices. Divided into three key sections, Part One introduces the reader to the safety and environmental impacts of the nuclear industry. Part Two reviews recent technological and methodological approaches to enhancing safety, as well as reducing the carbon footprint of both individual processes and integrated facilities. Topics covered include waste processing, transmutation and decommissioning. Part Three consider potential management schemes for special waste from innovative sources, and wastes that contain emerging contaminants, including waste recycling opportunities. Nuclear Waste Management Facilities: Advances, Environmental Impacts, and Future Prospects is a crucial tool needed to implement the safest and most environmentally considerate best practices within nuclear waste management facilities. - Presents recent approaches used to assess and improve the safety and reduce the environmental impacts of nuclear waste management facilities - Offers technical guidance to support the development and defense of the environmental impact assessment (EIA) and Safety Cases to support the waste management facilities licensing throughout their lifecycles - Highlights the future perspectives for wastes produced from innovative reactors and wastes containing emerging contaminants, and recycling opportunities
Geological Repository Systems for Safe Disposal of Spent Nuclear Fuels and Radioactive Waste, Second Edition, critically reviews state-of-the-art technologies and scientific methods relating to the implementation of the most effective approaches to the long-term, safe disposition of nuclear waste, also discussing regulatory developments and social engagement approaches as major themes. Chapters in Part One introduce the topic of geological disposal, providing an overview of near-surface, intermediate depth, and deep borehole disposal, spanning low-, medium- and high-level wastes. Part Two addresses the different types of repository systems – crystalline, clay, and salt, also discussing methods of site surveying and construction. The critical safety issue of engineered barrier systems is the focus of Part Three, with coverage ranging from nuclear waste canisters, to buffer and backfill materials. Lastly, Parts Four and Five focus on safety, security, and acceptability, concentrating on repository performance assessment, then radiation protection, environmental monitoring, and social engagement. Comprehensively revised, updated, and expanded with 25% new material on topics of current importance, this is the standard reference for all nuclear waste management and geological repository professionals and researchers. - Contains 25% more material on topics of current importance in this new, comprehensive edition - Fully updated coverage of both near-surface/intermediate depth, and deep borehole disposal in one convenient volume - Goes beyond the scientific and technical aspects of disposal to include the political, regulatory, and societal issues involved, all from an international perspective
The reactors around the world have produced more than 2000 tonnes of plutonium, contained in spent fuel or as separated forms through reprocessing. Disposition of fissile materials has become a primary concern of nuclear non-proliferation efforts worldwide. There is a significant interest in IAEA Member States to develop proliferation resistant nuclear fuel cycles for incineration of plutonium such as inert matrix fuels (IMFs). This publication reviews the status of potential IMF candidates and describes several identified candidate materials for both fast and thermal reactors: MgO, ZrO2, SiC, Zr alloy, SiAl, ZrN; some of these have undergone test irradiations and post irradiation examination. Also discussed are modelling of IMF fuel performance and safety analysis. System studies have identified strategies for both implementation of IMF fuel as homogeneous or heterogeneous phases, as assemblies or core loadings and in existing reactors in the shorter term, as well as in new reactors in the longer term.
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.