Uranium Processing and Properties describes developments in uranium science, engineering and processing and covers a broad spectrum of topics and applications in which these technologies are harnessed. This book offers the most up-to-date knowledge on emerging nuclear technologies and applications while also covering new and established practices for working with uranium supplies. The book also aims to provide insights into current research and processing technology developments in order to stimulate and motivate innovation among readers. Topics covered include casting technology, plate and sheet rolling, machining of uranium and uranium alloys, forming and fabrication techniques, corrosion kinetics, nondestructive evaluation and thermal modeling.

This book addresses the linear and nonlinear two-phase stability of the one-dimensional Two-Fluid Model (TFM) material waves and the numerical methods used to solve it. The TFM fluid dynamic stability is a problem that remains open since its inception more than forty years ago. The difficulty is formidable because it involves the combined challenges of two-phase topological structure and turbulence, both nonlinear phenomena. The one dimensional approach permits the separation of the former from the latter.The authors first analyze the kinematic and Kelvin-Helmholtz instabilities with the simplified one-dimensional Fixed-Flux Model (FFM). They then analyze the density wave instability with the well-known Drift-Flux Model. They demonstrate that the Fixed-Flux and Drift-Flux assumptions are two complementary TFM simplifications that address two-phase local and global linear instabilities separately. Furthermore, they demonstrate with a well-posed FFM and a DFM two cases of nonlinear two-phase behavior that are chaotic and Lyapunov stable. On the practical side, they also assess the regularization of an ill-posed one-dimensional TFM industrial code. Furthermore, the one-dimensional stability analyses are applied to obtain well-posed CFD TFMs that are either stable (RANS) or Lyapunov stable (URANS), with the focus on numerical convergence.

By drawing together the current theoretical and experimental understanding of the phenomena of delayed hydride cracking (DHC) in zirconium alloys, The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Components: Delayed Hydride Cracking provides a detailed explanation focusing on the properties of hydrogen and hydrides in these alloys. Whilst the emphasis lies on zirconium alloys, the combination of both the empirical and mechanistic approaches creates a solid understanding that can also be applied to other hydride forming metals. This up-to-date reference focuses on documented research surrounding DHC, including current methodologies for design and assessment of the results of periodic in-service inspections of pressure tubes in nuclear reactors. Emphasis is placed on showing how our understanding of DHC is supported by progress in general understanding of such broad fields as the study of hysteresis associated with first order phase transformations, phase relationships in coherent crystalline metallic solids, the physics of point and line defects, diffusion of substitutional and interstitial atoms in crystalline solids, and continuum fracture and solid mechanics. Furthermore, an account of current methodologies is given illustrating how such understanding of hydrogen, hydrides and DHC in zirconium alloys underpins these methodologies for assessments of real life cases in the Canadian nuclear industry. The all-encompassing approach makes The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Component: Delayed Hydride Cracking an ideal reference source for students, researchers and industry professionals alike.

These proceedings present the latest information on software reliability, industrial safety, cyber security, physical protection, testing and verification for nuclear power plants. The papers were selected from more than 80 submissions and presented at the First International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection for Nuclear Power Plants, held in Yinchuan, China on May 30 - June 1, 2016. The primary aim of this symposium was to provide a platform to facilitate the discussion for comprehension, application and management of digital instrumentation, control systems and technologies in nuclear power plants. The book reflects not only the state of the art and latest trends in nuclear instrumentation and control system technologies, but also China's increasing influence in this area. It is a valuable resource for both practitioners and academics working in the field of nuclear instrumentation, control systems and other safety-critical systems, as well as nuclear power plant managers, public officials and regulatory authorities.

Unlike existing books of nuclear reactor physics, nuclear engineering and nuclear chemical engineering this book covers a complete description and evaluation of nuclear fission power generation. It covers the whole nuclear fuel cycle, from the extraction of natural uranium from ore mines, uranium conversion and enrichment up to the fabrication of fuel elements for the cores of various types of fission reactors. This is followed by the description of the different fuel cycle options and the final storage in nuclear waste repositories. In addition the release of radioactivity under normal and possible accidental conditions is given for all parts of the nuclear fuel cycle and especially for the different fission reactor types.

This book is aimed at Health Physicists wishing to gain a better understanding of the principles and practices associated with a light water reactor (LWR) radiation protection program. The role of key program elements is presented in sufficient detail to assist practicing radiation protection professionals in improving and strengthening their current program. Details related to daily operation and discipline areas vital to maintaining an effective LWR radiation protection program are presented. Programmatic areas and functions important in preventing, responding to, and minimizing radiological incidents and the importance of performing effective incident evaluations and investigations are described. Elements that are integral in ensuring continuous program improvements are emphasized throughout the text.

The second edition of this book includes the most up-to-date details on the advantages of Nuclear Air-Brayton Power Plant Cycles for advanced reactors. It demonstrates significant advantages for typical sodium cooled reactors and describes how these advantages will grow as higher temperature systems (molten salts) are developed. It also describes how a Nuclear Air-Brayton system can be integrated with significant renewable (solar and wind) energy systems to build a low carbon grid. Starting with basic principles of thermodynamics as applied to power plant systems, it moves on to describe several types of Nuclear Air-Brayton systems that can be employed to meet different requirements. It provides estimates of component sizes and performance criteria for Small Modular Reactors (SMR). This book has been revised to include updated tables and significant new results that have become available for intercooled systems in the time since the previous edition published. In this edition also, the steam tables have been updated and Chapters 9 and 10 have been rewritten to keep up with the most up-to- date technology and current research.

"Tokamak Engineering Mechanics" offers concise and thorough coverage of engineering mechanics theory and application for tokamaks, and the material is reinforced by numerous examples. Chapter topics include general principles, static mechanics, dynamic mechanics, thermal fluid mechanics and multiphysics structural mechanics of tokamak structure analysis. The theoretical principle of the design and the methods of the analysis for various components and load conditions are presented, while the latest engineering technologies are also introduced. The book will provide readers involved in the study of mechanical/fusion engineering with a general understanding of tokamak engineering mechanics.
Yuntao Song is Head of the Tokamak Design Division at the Institute of Plasma Physics, Chinese Academic of Science (ASIPP), China.

This book focuses on tritium as a fuel for fusion reactors and a next-generation energy source. Following an introduction of tritium as a hydrogen radioisotope, important issues involved in establishing safe and economical tritium fuel cycles including breeding for a fusion reactor are summarized; these include the handling of large amounts of tritium: confinement, leakage, contamination, permeation, regulation and tritium accountancy, and impacts on surrounding areas. Targeting and encouraging the students and technicians who will design and operate fusion reactors in the near future, this book offers a valuable resource on tritium science and technology.

Nuclear and radioactive agents are considerable concerns especially after the early 1990s and more attention has been focused on the radiation detection technologies. This book comprises the selected presentations of NATO Advanced Training Course held 26-30 May 2008 in Mugla, Turkey. The contributions represent a wide range of documents related to control, monitoring and measurement methods of nuclear / radioactive isotopes and agents for both fundamental and applied works dealing with their use for different purposes. This book presents environmental data from many locations of different countries and also contains the contributions in the detection/monitoring programs of some authors from CIS countries.

The basic goal of this book is to deal with recent developments and applications of environmental monitoring and measurement techniques of environmental radionuclides and nuclear agents as well as the auxiliary techniques. The many recent examples contributed by authors will be useful in monitoring/ measurement studies of radioactive/nuclear agents in the present environment, and can help, not only in carrying out outdoor and laboratory experiments, but also in protection of possible sources of radionuclides and nuclear agents. Especially the contributions of experts and specialists involved in this book assured the highest level of knowledge in the field of techniques for the detection of radioactive and nuclear agents.

Introduces the concept of combined cycles for next generation nuclear power plants, explaining how recent advances in gas turbines have made these systems increasingly desirable for efficiency gains and cost-of-ownership reduction. Promulgates modelling and analysis techniques to identify opportunities for increased thermodynamic efficiency and decreased water usage over current Light Water Reactor (LWR) systems. Examines all power conversion aspects, from the fluid exiting the reactor to energy releases into the environment, with special focus on heat exchangers and turbo-machinery. Provides examples of small projects to facilitate nuanced understanding of the theories and implementation of combined-cycle nuclear plants. This book explores combined cycle driven efficiency of new nuclear power plants and describes how to model and analyze a nuclear heated multi-turbine power conversion system operating with atmospheric air as the working fluid. The included studies are intended to identify paths for future work on next generation nuclear power plants (GEN-IV), leveraging advances in natural-gas-fired turbines that enable coupling salt-cooled, helium-cooled, and sodium-cooled reactors to a Nuclear Air-Brayton Combined Cycle (NACC). These reactors provide the option of operating base-load nuclear plants with variable electricity output to the grid using natural gas or stored heat to produce peak power. The author describes overall system architecture, components and detailed modelling results of Brayton-Rankine Combined Cycle power conversion systems and Recuperated Brayton Cycle systems, since they offer the highest overall energy conversion efficiencies. With ever-higher temperatures predicted in GEN-IV plants, this book's investigation of potential avenues for thermodynamic efficiency gains will be of great interest to nuclear engineers and researchers, as well as power plant operators and students.

A vast amount has been written on climate change and what should be our response. Rise and Fall of the Carbon Civilisation suggests that most of this literature takes a far too optimistic position regarding the potential for conventional mitigation solutions to achieve the deep cuts in greenhouse gases necessary in the limited time frame we have available. In addition, global environmental problems, as exemplified by climate change, and global resource problems - such as fossil fuel depletion or fresh water scarcity - have largely been seen as separate issues. Further, proposals for solution of these problems often focus at the national level, when the problems are global. The authors argue that the various challenges the planet faces are both serious and interconnected. Rise and Fall of the Carbon Civilisation takes a global perspective in its treatment of various solutions: * renewable energy; * nuclear energy; * energy efficiency; * carbon sequestration; and * geo-engineering. It also addresses the possibility that realistic solutions cannot be achieved until the fundamentally ethical question of global equity - both across nations today and also inter-generational - is fully addressed. Such an approach will also involve reorienting the global economy away from an emphasis on growth and toward the direct satisfaction of basic human needs for all the Earth's people. Rise and Fall of the Carbon Civilisation is aimed at the many members of the public with an awareness of climate change, but who wish to find out more about how we need to respond to the challenge. It will also be of interest to technical professionals, as well as postgraduate students and researchers, from the environmental and engineering science sectors.

This thesis describes a proof-of-principle experiment demonstrating a technique for stable isotope enrichment called Magnetically Activated and Guided Isotope Separation (MAGIS). Over the past century many enriched isotopes have become available, thanks largely to electromagnetic separators called calutrons. Due to substantial maintenance and operating costs, the United States decommissioned the last of its calutrons in 1998, leading to demand for alternative methods of isotope separation. The work presented here suggests the promise for MAGIS as a viable alternative to the calutrons.The MAGIS technique combines optical pumping with a scalable magnetic field gradient to enrich atoms of a specific isotope in an atomic beam. Benchmarking this work against the calutron using lithium as a test case, the author demonstrated comparable enrichment in a manner that should scale to the production of similar quantities, while requiring vastly less energy input.

The Magnitude 9 Great East Japan Earthquake on March 11, 2011, followed by a massive tsunami struck TEPCO's Fukushima Daiichi Nuclear Power Station and triggered an unprecedented core melt/severe accident in Units 1 - 3. The radioactivity release led to the evacuation of local residents, many of whom still have not been able to return to their homes. As a group of nuclear experts, the Atomic Energy Society of Japan established the Investigation Committee on the Nuclear Accident at the Fukushima Daiichi Nuclear Power Station, to investigate and analyze the accident from scientific and technical perspectives for clarifying the underlying and fundamental causes, and to make recommendations. The results of the investigation by the AESJ Investigation Committee has been compiled herewith as the Final Report. Direct contributing factors of the catastrophic nuclear incident at Fukushima Daiichi NPP initiated by an unprecedented massive earthquake/ tsunami - inadequacies in tsunami measures, severe accident management, emergency response, accident recovery and mitigations - and the underlying factors - organizational issues, etc., have been clarified and recommendations in the following areas have been made. - Nuclear safety fundamentals - Direct factors of the accident - Organizational aspects - Common items (R&D, International cooperation, human resources management) - Post-accident management/recovery from the accident.

Concerns over the planet's limited energy sources are not new. For the past half-century, scientists from around the world have explored substitutes for fossil fuels. Among them, developed nations have invested considerable resources in the development of nuclear fusion technology. Thus, in 1978, scientists and engineers from Europe, Japan, the United States, and the former Soviet Union joined together under the banner of the INTOR Workshop (INternational group working on a TOkamak Reactor) to share their individual research on nuclear fusion's viability as an energy source. Their ten years of cooperative work on the design and development possibilities for harnessing nuclear energy planted the seeds for the International Thermonuclear Experimental Reactor (ITER), construction of which began in 2008 and whose goal it is to demonstrate the scientific and technical feasibility of fusion power. Weston Stacey served as the INTOR Workshop's vice-chairman (and U.S. representative) and kept a journal in which he detailed both the scientific participants' technical work as well as their more political interactions. In this first person narrative, Stacey provides an accessible account (introducing explanatory material when necessary) of the research and development activities conducted to determine the viability of designing, constructing, and operating a tokamak experimental power reactor. Of more human interest were the obstacles the Workshop leaders and participants faced as they advanced their own countries' priorities while striving to make progress on the global future of nuclear fusion technology. Personal anecdotes illuminate the mixing of cultures and the challenges presented by the Cold War's unique political climate. While the focus of the book centers on the history of the INTOR Workshop, Stacey paints a full picture of the people and places involved in the work, how decisions were made, and how these efforts laid the groundwork for ITER's subsequent development. This text will appeal not only to those studying fusion science and engineering, but to anyone interested in a unique story of how international relations and scientific study intersect, ultimately one of collaboration for the sake of a common goal.

This book is a complete update of the classic 1981 FAST BREEDER REACTORS textbook authored by Alan E. Waltar and Albert B. Reynolds, which, along with the Russian translation, served as a major reference book for fast reactors systems. Major updates include transmutation physics (a key technology to substantially ameliorate issues associated with the storage of high-level nuclear waste ), advances in fuels and materials technology(including metal fuels and cladding materials capable of high-temperature and high burnup), and new approaches to reactor safety (including passive safety technology), New chapters on gas-cooled and lead-cooled fast spectrum reactors are also included.

Key international experts contributing to the text include Chaim Braun, (Stanford University) Ronald Omberg, (Pacific Northwest National Laboratory, Massimo Salvatores (CEA, France), Baldev Raj, (Indira Gandhi Center for Atomic Research, India), John Sackett (Argonne National Laboratory), Kevan Weaver, (TerraPower Corporation), James Seinicki(Argonne National Laboratory). Russell Stachowski (General Electric), Toshikazu Takeda (University of Fukui, Japan), and Yoshitaka Chikazawa (Japan Atomic Energy Agency). "

For the first time a book has been written on the technological and scientific knowledge, acquired during, buiding , operation and even dismantling of the Superphenix plant. This reactor remains today the most powerful sodium fast breeder reactor operated in the world.(1200 MWe). The last fast breeder reactor operated in the world is BN 800 in Russia that reached his nominal power (800 MWe) in 2016. Joel Guidez began his career in the field of sodium-cooled fast reactors after leaving Ecole Centrale-Paris, in 1973. He has held various positions at Cadarache, Phenix and Superphenix, including as the head of the thermal hydraulic laboratory conducting tests for Phenix, Superphenix and the EFR European Fast Reactor project. He was also head of the OSIRIS research reactor, located at SACLAY, and of the HFR European Commission reactor, located in the Netherlands and spent two years as nuclear attache at the French embassy in Berlin. His 2012 book "Phenix: the experience feedback" was translated into English and republished in 2013, and this new book on Superphenix is in the same spirit of thematic analysis of a reactor experience feedback. Gerard Prele graduated from the Ecole Centrale-Lyon and entered EDF and the field of sodium-cooled fast reactors in 1983. In 1985 he joined Superphenix, where he was a duty engineer and was later in charge of safety. He has held various positions at Superphenix and Phenix and was a fast neutron reactor (SFR) engineer at the EDF Centre Lyonnais d'Ingenierie (CLI). He worked as Safety Security Environment and Radiation Protection Mission head in Superphenix at the beginning of dismantling and then in the field of PWR for two years. Since 2006 he has been involved in the Gen IV and the SFR/Astrid projects. Today, as an SFR/system and operations expert, one of his major roles is assisting the CEA in the preliminary design of the ASTRID reactor.

For operators of nuclear research facilities, it is of particular importance to investigate minor incidents: indeed, as safety demonstrations are generally based on the presence of several independent "lines of defence," only through attentive investigation of every occurrence, usually minor and of no consequence, can the level of trust placed in each of these defensive lines be confirmed, or the potential risks arising out of a possible weakness in the system be anticipated.

The efficiency of the system is based on a rigorous procedure: stringent attention to all incidents, consideration of the potential consequences of the incidents in their most pessimistic scenarios, and promotion of a broad conception of transpositions of the events, in time and space, for experience feedback.

This efficiency presumes motivation on the part of all those involved, hence the importance of dissociating from the concept of an "incident" any notion of "error" or "blame" both in internal analysis and in public communications.

The nuclear industry has developed some very progressive tools for experience feedback, which could interest also management of other technological risks.

This book presents the proceedings of a NATO Advanced Workshop dedicated to this important matter of concern.

In this global wake-up call, nuclear physicist Jeff Eerkens explores remedies for the impending energy crisis, when oil and natural gas are depleted. The Nuclear Imperative demonstrates that solar, wind, and biomass power are incapable of supplying the enormous quantities of electricity and heat needed for manufacturing portable synthetic fuels to replace our current use of fossil fuels. It offers a fresh look at uranium-produced energy as the optimal affordable solution.

Energy comes in many shapes and forms, from wind, solar power, geothermal, and biomass to coal, natural gas, and petroleum. The energy we consume is constantly changing, but the use of these resources-whether renewable or nonrenewable-has long-term impacts on our planet. While there has been this recent shift to renewable energy within the United States, the worldwide demand for all energy types continues to increase at a rapid rate. In fact, it has increased by 84% over the past twenty years. Despite their dwindling supply, these resources are still heavily relied on today. Coal still accounts for 30% of the electricity generated by the United States, even though natural gas is now the primary energy used to produce electricity. Likewise, only 7% of electricity usage worldwide is linked to solar and wind energy. In The Changing Energy Mix, Paul F. Meier compares twelve renewable and nonrenewable energy types using twelve common technical criteria. These criteria span projected reserves, cost to the consumer and supplier, energy balances, environmental issues, land area required, and lasting impacts. While explaining the pros and cons of these resources, Meier takes readers through the history of energy in the United States and world. He provides insight into energy sources, such as wind-powered and solar-powered electricity (which did not exist until the mid and late 80s, respectively), and he explains the constantly evolving world of energy. Breaking down the potential promises and struggles of transitioning to a more renewable energy-based economy, Meier explains the positive and negative implications of these various sources of energy. The resulting book equips readers with a unique understanding of the history, availability, technology, implementation cost, and concerns of renewable and nonrenewable energy.

A great number of nuclear submarines are due to be decommissioned before 2000. The political decisions surrounding the disposal of nuclear compartments, radioactive wastes and spent fuel differ appreciably between the countries that own the boats. The decision makers involved thus need help in comparing and assessing alternative options for the decommissioning of their nuclear submarine fleets. The present volume offers such assistance, with its discussions of the risks associated with long-term water storage of the boats, radioactive and chemical contamination, spent fuel and waste management, and handling and recycling reactor compartments.

The aim of this book is to summarize probabilistic safety assessment (PSA) of nuclear power plants (NPPs), and to demonstrate that NPPs can be considered a safe method of producing energy, even in light of the Fukushima accident. The book examines level 1 and 2 full power, low power and shutdown probabilistic safety assessment of WWER440 reactors, and summarizes the author s experience gained during the last 35 years. It provides useful examples taken from PSA training courses delivered by the author and organized by the International Atomic Energy Agency. Such training courses were organised in Argonne National Laboratory (Chicago, IL, USA), Abdus Salaam International Centre for Theoretical Physics (Trieste, Italy) in Malaysia, Vietnam and Jordan to support experts from developing countries.

The role of probabilistic safety assessment (PSA) for NPPs (nuclear power plants) is an estimation of the risks in absolute terms and in comparison with other risks of the technical and the natural world. Plant-specific PSAs are being prepared for the NPPs and being applied for detection of weaknesses, design improvement and backfitting, incident analysis, accident management, emergency preparedness, prioritization of research & development and support of regulatory activities.

There are three levels of PSA, being performed for full power and low power operation and shutdown operating modes of the plant: Level 1 PSA, Level 2 PSA and Level 3 PSA. The nuclear regulatory authorities do not require the level 3 PSA for NPPs in the member countries of the European Union. So, only limited number of NPPs has available the level 3 PSA in Europe. However, in the light of the Fukushima accident the performance of such analyses is strongly recommended in the future. This book is intended for professionals working in the nuclear industry, and researchers and students interested in nuclear research.

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