Advances In Nuclear Fuel

Advances in Nuclear Fuel Chemistry presents a high-level description of nuclear fuel chemistry based on the most recent research and advances. Dr. Markus H.A. Piro and his team of global, expert contributors cover all aspects of both the conventional uranium-based nuclear fuel cycle and non-conventional fuel cycles, including mining, refining, fabrication, and long-term storage, as well as emerging nuclear technologies, such as accident tolerant fuels and molten salt materials. Aimed at graduate students, researchers, academics and practicing engineers and regulators, this book will provide the reader with a single reference from which to learn the fundamentals of classical thermodynamics and radiochemistry. Consolidates the latest research on nuclear fuel chemistry into one comprehensive reference, covering all aspects of traditional and non-traditional nuclear fuel cycles Includes contributions from world-renowned experts from many countries representing government, industry and academia Covers a variety of fuel designs, including conventional uranium dioxide, mixed oxides, research reactor fuels, and molten salt fuels Written by experts with hands-on experience in the development of such designs

Worldwide there are more than 430 nuclear power plants operating and more plants are being constructed or planned for construction. For nuclear power to be sustainable the nuclear fuel must be sustainable and there should be adequate nuclear fuel waste management program. Continuous technological advances will lead towards sustainable nuclear fuel through closed fuel cycles and advance fuel development. This focuses on challenges and issues that need to be addressed for better performance and safety of nuclear fuel in nuclear plants. These focused areas are on development of high conductivity new fuels, radiation induced corrosion, fuel behavior during abnormal events in reactor, and decontamination of radioactive material.

Advanced separations technology is key to closing the nuclear fuel cycle and relieving future generations from the burden of radioactive waste produced by the nuclear power industry. Nuclear fuel reprocessing techniques not only allow for recycling of useful fuel components for further power generation, but by also separating out the actinides, lanthanides and other fission products produced by the nuclear reaction, the residual radioactive waste can be minimised. Indeed, the future of the industry relies on the advancement of separation and transmutation technology to ensure environmental protection, criticality-safety and non-proliferation (i.e., security) of radioactive materials by reducing their long-term radiological hazard. Advanced separation techniques for nuclear fuel reprocessing and radioactive waste treatment provides a comprehensive and timely reference on nuclear fuel reprocessing and radioactive waste treatment. Part one covers the fundamental chemistry, engineering and safety of radioactive materials separations processes in the nuclear fuel cycle, including coverage of advanced aqueous separations engineering, as well as on-line monitoring for process control and safeguards technology. Part two critically reviews the development and application of separation and extraction processes for nuclear fuel reprocessing and radioactive waste treatment. The section includes discussions of advanced PUREX processes, the UREX+ concept, fission product separations, and combined systems for simultaneous radionuclide extraction. Part three details emerging and innovative treatment techniques, initially reviewing pyrochemical processes and engineering, highly selective compounds for solvent extraction, and developments in partitioning and transmutation processes that aim to close the nuclear fuel cycle. The book concludes with other advanced techniques such as solid phase extraction, supercritical fluid and ionic liquid extraction, and biological treatment processes. With its distinguished international team of contributors, Advanced separation techniques for nuclear fuel reprocessing and radioactive waste treatment is a standard reference for all nuclear waste management and nuclear safety professionals, radiochemists, academics and researchers in this field. A comprehensive and timely reference on nuclear fuel reprocessing and radioactive waste treatment Details emerging and innovative treatment techniques, reviewing pyrochemical processes and engineering, as well as highly selective compounds for solvent extraction Discusses the development and application of separation and extraction processes for nuclear fuel reprocessing and radioactive waste treatment

Advances in Nuclear Science and Technology, Volume 9 provides information pertinent to the fundamental aspects of nuclear science and technology. This book discusses the safe and beneficial development of land-based nuclear power plants. Organized into five chapters, this volume begins with an overview of the possible consequences of a large-scale release of radioactivity from a nuclear reactor in the event of a serious accident. This text then discusses the extension of conventional perturbation techniques to multidimensional systems and to high-order approximations of the Boltzmann equation. Other chapters consider details of probability treatment of the conventionally assumed loss-of-pressure accident to a modern gas-cooled reactor. This book discusses as well details of reliability analysis of a typical electromechanical protective system. The final chapter deals with the computer applications and the need for standardization as both computing and nuclear energy shifted from research and development to industry status. This book is a valuable resource for reactor physicists, engineers, scientists, and research workers.

Continuous and rapid advancements in nuclear fuels present new questions, greater challenges and vast new opportunities in this field. Globally, there are more than 430 nuclear power plants in service and more plants are being developed or planned for construction. For nuclear power to be viable nuclear fuel, it must be sustainable and there should be a competent nuclear fuel waste management program. Constant technological developments will pave the way towards viable nuclear fuel through blocked fuel cycles and advance fuel development. This book focuses on topics and issues that need to be addressed for better production and security of nuclear fuel in nuclear plants.

Advances in Nuclear Science and Technology, Volume 1 provides an authoritative, complete, coherent, and critical review of the nuclear industry. This book covers a variety of topics, including nuclear power stations, graft polymerization, diffusion in uranium alloys, and conventional power plants. Organized into seven chapters, this volume begins with an overview of the three stages of the operation of a power plant, either nuclear or conventionally fueled. This text then examines the major problems that face the successful development of commercial nuclear power plants. Other chapters consider the synthesis of graft copolymers by radiation-induced graft polymerization. This book discusses as well the processes of technical importance in the nuclear field, such as the bonding of fuel materials to cladding, or the release of fission gases from fuel elements. The final chapter deals with the effects of nuclear radiation in causing chemical changes in matter. This book is a valuable resource for scientists and engineers.

The continued presence of highly enriched uranium (HEU) in civilian installations such as research reactors poses a threat to national and international security. Minimization, and ultimately elimination, of HEU in civilian research reactors worldwide has been a goal of U.S. policy and programs since 1978. Today, 74 civilian research reactors around the world, including 8 in the United States, use or are planning to use HEU fuel. Since the last National Academies of Sciences, Engineering, and Medicine report on this topic in 2009, 28 reactors have been either shut down or converted from HEU to low enriched uranium fuel. Despite this progress, the large number of remaining HEU-fueled reactors demonstrates that an HEU minimization program continues to be needed on a worldwide scale. Reducing the Use of Highly Enriched Uranium in Civilian Research Reactors assesses the status of and progress toward eliminating the worldwide use of HEU fuel in civilian research and test reactors.