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Nuclear engineers advancing the energy transition are understanding more about the next generation of nuclear plants; however, it is still difficult to access all the critical types, concepts, and applications in one location. Advanced Reactor Concepts (ARC): A New Nuclear Power Plant Perspective Producing Energy gives engineers and nuclear engineering researchers the comprehensive tools to get up to date on the latest technology supporting generation IV nuclear plant systems. After providing a brief history of this area, alternative technology is discussed such as electromagnetic pumps, heat pipes as control devices, Nuclear Air-Brayton Combined Cycles integration, and instrumentation helping nuclear plants to provide dispatchable electricity to the grid and heat to industry. Packed with examples of all the types, benefits, and challenges involved, Advanced Reactor Concepts (ARC) delivers the go-to reference that engineers need to advance safe nuclear energy as a low-carbon option. - Describes theory and concepts on generation IV technology such as advanced reactor concepts (ARC) and electromagnetic pumps, and compares different types and sizes. - Sets out the energy transition with critical carbon-free technology that can supplement intermittent power sources such as wind and solar. - Explains alternative heat storage technology, including Nuclear Air-Brayton Combined Cycles. - Introduces advanced main instrumentation systems for in-core probes.

Research reactor fuel technology continues to evolve, driven in part by international efforts to develop high density fuels to enable the conversion of more reactors from highly enriched uranium (HEU) to low enriched uranium (LEU) fuels. These high density fuels may offer economic benefits for research reactors, despite being more expensive initially, because they offer the prospect of higher per-assembly burnup, thus reducing the number of assemblies that must be procured, and more flexibility in terms of spent fuel management compared to the currently qualified and commercially available LEU silicide fuels. Additionally, these new fuels may offer better performance characteristics. This publication provides a preliminary evaluation of the impacts on research reactor performance and fuel costs from using high density fuel. Several case studies are presented and compared to illustrate these impacts.

El objeto de este libro es la descripción de los principios fundamentales, científicos y tecnológicos de los sistemas de reactores nucleares. Se dedica principal atención al proyecto de reactores y comportamiento de los mismos en relación con el proceso de fisión y radiaciones asociadas, con preferencia a otras zonas de Ingeniería que no son exclusivas de los reactores nucleares.

Reactor physics is the discipline devoted to the study of interactions between neutrons and matter in a nuclear reactor. This third edition of Applied Reactor Physics, addresses the fundamentals of reactor physics. Legacy numerical techniques are introduced with sufficient details to help readers implement them in Matlab. The fundamental approaches presented here provide a solid foundation for the more advanced and proprietary techniques that readers may encounter in production environments. Applied Reactor Physics emphasizes the algorithmic nature of the numerical solution techniques used in reactor physics. Many numerical solution approaches described in the book are accompanied by Matlab scripts, and readers are encouraged to write short Matlab scripts of their own in order to solve the end-of-chapter exercises. The third edition includes key improvements in the text, a completely rewritten appendix on numerical methods, new end-of-chapter exercises, and an extended bibliography.

Handbook of Small Modular Nuclear Reactors, Second Edition is a fully updated comprehensive reference on Small Modular Reactors (SMRs), which reflects the latest research and technological advances in the field from the last five years. Editors Daniel T. Ingersoll and Mario D. Carelli, along with their team of expert contributors, combine their wealth of collective experience to update this comprehensive handbook that provides the reader with all required knowledge on SMRs, expanding on the rapidly growing interest and development of SMRs around the globe. This book begins with an introduction to SMRs for power generation, an overview of international developments, and an analysis of Integral Pressurized Water Reactors as a popular class of SMRs. The second part of the book is dedicated to SMR technologies, including physics, components, I&C, human-system interfaces and safety aspects. Part three discusses the implementation of SMRs, covering economic factors, construction methods, hybrid energy systems and licensing considerations. The fourth part of the book provides an in-depth analysis of SMR R&D and deployment of SMRs within eight countries, including the United States, Republic of Korea, Russia, China, Argentina, and Japan. This edition includes brand new content on the United Kingdom and Canada, where interests in SMRs have increased considerably since the first edition was published. The final part of the book adds a new analysis of the global SMR market and concludes with a perspective on SMR benefits to developing economies. This authoritative and practical handbook benefits engineers, designers, operators, and regulators working in nuclear energy, as well as academics and graduate students researching nuclear reactor technologies. - Presents the latest research on SMR technologies and global developments - Includes new case study chapters on the United Kingdom and Canada and a chapter on global SMR markets - Discusses new technologies such as floating SMRs and molten salt SMRs

Nuclear Reactor Technology Development and Utilization presents the theory and principles of the most common advanced nuclear reactor systems and provides a context for the value and utilization of nuclear power in a variety of applications both inside and outside a traditional nuclear setting. As countries across the globe realize their plans for a sustainable energy future, the need for innovative nuclear reactor design is increasing, and this book will provide a deep understanding of how these technologies can aid in a region's goal for clean and reliable energy. Dr Khan and Dr Nakhabov, alongside their team of expert contributors, discuss a variety of important topics, including nuclear fuel cycles, plant decommissioning and hybrid energy systems, while considering a variety of diverse uses such as nuclear desalination, hydrogen generation and radioisotope production. Knowledge acquired enables the reader to conduct further research in academia and industry, and apply the latest design, development, integration, safety and economic guidance to their work and research. - Combines reactor fundamentals with a contemporary look at evolving trends in the design of advanced reactors and their application to both nuclear and non-nuclear uses - Analyses the latest research and uses of hybrid systems which bring together nuclear technology with renewable energy technologies - Presents applications, economic factors and an analysis of sustainability factors in one comprehensive resource

Modelling of Nuclear Reactor Multiphysics: From Local Balance Equations to Macroscopic Models in Neutronics and Thermal-Hydraulics is an accessible guide to the advanced methods used to model nuclear reactor systems. The book addresses the frontier discipline of neutronic/thermal-hydraulic modelling of nuclear reactor cores, presenting the main techniques in a generic manner and for practical reactor calculations.The modelling of nuclear reactor systems is one of the most challenging tasks in complex system modelling, due to the many different scales and intertwined physical phenomena involved. The nuclear industry as well as the research institutes and universities heavily rely on the use of complex numerical codes. All the commercial codes are based on using different numerical tools for resolving the various physical fields, and to some extent the different scales, whereas the latest research platforms attempt to adopt a more integrated approach in resolving multiple scales and fields of physics. The book presents the main algorithms used in such codes for neutronic and thermal-hydraulic modelling, providing the details of the underlying methods, together with their assumptions and limitations. Because of the rapidly expanding use of coupled calculations for performing safety analyses, the analysists should be equally knowledgeable in all fields (i.e. neutron transport, fluid dynamics, heat transfer).The first chapter introduces the book's subject matter and explains how to use its digital resources and interactive features. The following chapter derives the governing equations for neutron transport, fluid transport, and heat transfer, so that readers not familiar with any of these fields can comprehend the book without difficulty. The book thereafter examines the peculiarities of nuclear reactor systems and provides an overview of the relevant modelling strategies. Computational methods for neutron transport, first at the cell and assembly levels, then at the core level, and for one-/two-phase flow transport and heat transfer are treated in depth in respective chapters. The coupling between neutron transport solvers and thermal-hydraulic solvers for coarse mesh macroscopic models is given particular attention in a dedicated chapter. The final chapter summarizes the main techniques presented in the book and their interrelation, then explores beyond state-of-the-art modelling techniques relying on more integrated approaches. - Covers neutron transport, fluid dynamics, and heat transfer, and their interdependence, in one reference - Analyses the emerging area of multi-physics and multi-scale reactor modelling - Contains 71 short videos explaining the key concepts and 77 interactive quizzes allowing the readers to test their understanding

This expanded new edition develops the theory of nuclear reactors from the fundamentals of fission to the operating characteristics of modern reactors. The first half of the book emphasizes reactor criticality analysis and all of the fundamentals that go into modern calculations. Simplified one group diffusion theory models are presented and extended into sophisticated multi-group transport theory models. The second half of the book deals with the two main topics of interest related to operating reactors – reactor kinetics/dynamics, and in-core fuel management. Additional chapters have been added to expand and bring the material up-to-date and include the utilization of more computer codes. Code models and detailed data sets are provided along with example problems making this a useful text for students and researchers wishing to develop an understanding of nuclear power and its implementation in today's modern energy spectrum.Covers the fundamentals of neutronic analysis for nuclear reactor systems to help understand nuclear reactor theory;Describes the benefits, uses, safety features, and challenges related to implementation of Small Modular Reactors;Provides examples, data sets, and code to assist the reader in obtaining mastery over the subjects.

This book highlights Small Modular Reactors (SMRs) as a viable alternative to the Nuclear Power Plants (NPPs), which have been used as desalination plant energy sources. SMRs have lower investment costs, inherent safety features, and increased availability compared to NPPs. The unique and innovative approach to implementation of SMRs as part of Gen-IV technology outlined in this book contributes to the application of nuclear power as a supplementary source to renewable energy. Discusses Gen-IV Power plants, their efficiency, cost effectiveness, safety, and methods to supply renewable energy;Presents Small Modular Reactors as a viable alternative to Nuclear Power Plants;Describes the benefits, uses, safety features, and challenges related to implementation of Small Modular Reactors.

Dynamics and Control of Nuclear Reactors presents the latest knowledge and research in reactor dynamics, control and instrumentation; important factors in ensuring the safe and economic operation of nuclear power plants. This book provides current and future engineers with a single resource containing all relevant information, including detailed treatments on the modeling, simulation, operational features and dynamic characteristics of pressurized light-water reactors, boiling light-water reactors, pressurized heavy-water reactors and molten-salt reactors. It also provides pertinent, but less detailed information on small modular reactors, sodium fast reactors, and gas-cooled reactors. - Provides case studies and examples to demonstrate learning through problem solving, including an analysis of accidents at Three Mile Island, Chernobyl and Fukushima Daiichi - Includes MATLAB codes to enable the reader to apply the knowledge gained to their own projects and research - Features examples and problems that illustrate the principles of dynamic analysis as well as the mathematical tools necessary to understand and apply the analysis Publishers Note: Table 3.1 has been revised and will be included in future printings of the book with the following data: Group Decay Constant, li (sec-1) Delayed Neutron Fraction (bi) 1 0.0124 0.000221 2 0.0305 0.001467 3 0.111 0.001313 4 0.301 0.002647 5 1.14 0.000771 6 3.01 0.000281 Total delayed neutron fraction: 0.0067

This book discusses advanced Small Modular Reactors (SMRs) as a way to provide safe, clean, and affordable nuclear power options. The advanced SMRs currently under development in the U.S. represent a variety of sizes, technology options and deployment scenarios. These advanced reactors, envisioned to vary in size from a couple megawatts up to hundreds of megawatts can be used for power generation, process heat, desalination, or other industrial uses. In-depth chapters describe how advanced SMRs offer multiple advantages, such as relatively small size, reduced capital investment, location flexibility, and provisions for incremental power additions. SMRs also offer distinct safeguards, security and nonproliferation advantages. The authors present a thorough examination of the technology and defend methods by which the new generation of nuclear power plants known as GEN-IV can safely be used as an efficient source of renewable energy. Provides a unique and innovative approach to the implementation of Small Modular Reactor as part of GEN-IV technology; Discusses how Small Modular Reactors (SMRs) can deliver a viable alternative to Nuclear Power Plants (NPPs);Presents an argument defending the need for nuclear power plant as a source of energy, its efficiency and cost effectiveness, as well as safety related issues.

This book addresses the topic of fractional-order modeling of nuclear reactors. Approaching neutron transport in the reactor core as anomalous diffusion, specifically subdiffusion, it starts with the development of fractional-order neutron telegraph equations. Using a systematic approach, the book then examines the development and analysis of various fractional-order models representing nuclear reactor dynamics, ultimately leading to the fractional-order linear and nonlinear control-oriented models. The book utilizes the mathematical tool of fractional calculus, the calculus of derivatives and integrals with arbitrary non-integer orders (real or complex), which has recently been found to provide a more compact and realistic representation to the dynamics of diverse physical systems.Including extensive simulation results and discussing important issues related to the fractional-order modeling of nuclear reactors, the book offers a valuable resource for students and researchersworking in the areas of fractional-order modeling and control and nuclear reactor modeling.

This comprehensive volume offers readers a progressive and highly detailed introduction to the complex behavior of neutrons in general, and in the context of nuclear power generation. A compendium and handbook for nuclear engineers, a source of teaching material for academic lecturers as well as a graduate text for advanced students and other non-experts wishing to enter this field, it is based on the author's teaching and research experience and his recognized expertise in nuclear safety.After recapping a number of points in nuclear physics, placing the theoretical notions in their historical context, the book successively reveals the latest quantitative theories concerning:• The slowing-down of neutrons in matter• The charged particles and electromagnetic rays• The calculation scheme, especially the simplification hypothesis• The concept of criticality based on chain reactions• The theory of homogeneous and heterogeneous reactors• The problem of self-shielding• The theory of the nuclear reflector, a subject largely ignored in literature• The computational methods in transport and diffusion theories Complemented by more than 400 bibliographical references, some of which are commented and annotated, and augmented by an appendix on the history of reactor physics at EDF (Electricité De France), this book is the most comprehensive and up-to-date introduction to and reference resource in neutronics and reactor theory.

This book examines the three most well-known and socially important nuclear accidents. Each of these accidents had significant, yet dramatically different, human and environmental impacts. Unique factors helped shape the overall pattern and scale of each disaster, but a major contributing factor was the different designs used for each reactor. Fukushima was a boiling water reactor (BWR), Chernobyl was a graphite moderated boiling water reactor, and TMI was a pressurized water reactor (PWR). This book traces the history of nuclear power and the development of each reactor type. We examine how GE's work with a sodium cooled design did not fare well with the US Navy, and led GE to promulgate the BWR design. We explore the Russian atomic bomb program, its use of graphite moderated reactors, and their design modifications to create power production units. We trace the developments in the US that led the US Navy to select the PWR design, and caused the PWR to be used for nearly 2/3 of all UScommercial reactors. In sum, the book uses the three major nuclear accidents as a lens to trace the technological history of nuclear energy production and to link these developments with long-term societal and environmental consequences. The book is intended for readers with an interest in nuclear power and nuclear disasters. The detailed and compelling account will appeal to both the expert and the interested lay-person.

This book describes the fast reactor (FR), a type of new reactor for nuclear plants, currently under research and development. The book targets young researchers and engineers who will be charged with commercializing this new type of reactor to lead to the development of new components and systems for improved plant reliability and economy. This volume also helps readers to understand the methods of integrating the power plant in its entirety, from the reactor core to all of the various systems and components, and teaches the way of thinking that forms the background of these methods. This background includes the various organizational and management issues that are encountered as projects move forward and will be explored in great detail based on actual design and construction experience with Japan's prototype FR, Monju.

This book covers the entire spectrum of the science and technology of nuclear reactor systems, from underlying physics, to next generation system applications and beyond. Beginning with neutron physics background and modeling of transport and diffusion, this self-contained learning tool progresses step-by-step to discussions of reactor kinetics, dynamics, and stability that will be invaluable to anyone with a college-level mathematics background wishing to develop an understanding of nuclear power. From fuels and reactions to full systems and plants, the author provides a clear picture of how nuclear energy works, how it can be optimized for safety and efficiency, and why it is important to the future.

This book describes recent technological developments in next generation nuclear reactors that have created renewed interest in nuclear process heat for industrial applications. The author's discussion mirrors the industry's emerging focus on combined cycle Next Generation Nuclear Plants'(NGNP) seemingly natural fit in producing electricity and process heat for hydrogen production. To utilize this process heat, engineers must uncover a thermal device that can transfer the thermal energy from the NGNP to the hydrogen plant in the most performance efficient and cost effective way possible. This book is written around that vital quest, and the author describes the usefulness of the Intermediate Heat Exchanger (IHX) as a possible solution. The option to transfer heat and thermal energy via a single-phase forced convection loop where fluid is mechanically pumped between the heat exchangers at the nuclear and hydrogen plants is presented, and challenges associated with this tacticare discussed. As a second option, heat pipes and thermosyphons, with their ability to transport very large quantities of heat over relatively long distance with small temperature losses, are also examined.

There is currently significant interest in the development of small modular reactors (SMRs) for the generation of both electricity and process heat. SMRs offer potential benefits in terms of better affordability and enhanced safety, and can also be sited more flexibly than traditional nuclear plants. Small Modular Reactors: Nuclear Power Fad or Future? reviews SMR features, promises, and problems, also discussing what lies ahead for reactors of this type. The book is organized into three major parts with the first part focused on the role of energy, especially nuclear energy, for global development. It also provides a brief history of SMRs. The second major part presents basic nuclear power plant terminology and then discusses in depth the attributes of SMRs that distinguish them from traditional nuclear plants. The third and final major section discusses the current interest in SMRs from a customer's perspective and delineates several remaining hurdles that must be addressed to achieve wide-spread SMR deployment. - Provides decision-makers in governments, business, and research with the needed background on small nuclear power and an overview of the current situation - Presents a balanced discussion of the many advantages of SMRs and the challenges they face - Written by a highly respected expert in the nuclear industry

Reactor Pressure Vessels (RPVs) contain the fuel and therefore the reaction at the heart of nuclear power plants. They are a life-determining structural component: if they suffer serious damage, the continued operation of the plant is in jeopardy. This book critically reviews irradiation embrittlement, the main degradation mechanism affecting RPV steels, and mitigation routes for managing the RPV lifetime. Part I reviews RPV design and fabrication in different countries, with an emphasis on the materials required, their important properties, and manufacturing technologies. Part II then considers RVP embrittlement in operational nuclear power plants using different reactors. Chapters are devoted to embrittlement in light-water reactors, including WWER-type reactors and Magnox reactors. Finally, Part III presents techniques for studying embrittlement, including irradiation simulation techniques, microstructural characterisation techniques, and probabilistic fracture mechanics. Irradiation Embrittlement of Reactor Pressure Vessels (RPVs) in Nuclear Power Plants provides a thorough review of an issue that is central to the safety of nuclear power generation. The book includes contributions from an international team of experts, and will be a useful resource for nuclear plant operators and managers, relevant regulatory and safety bodies, nuclear metallurgists and other academics in this field - Discusses reactor pressure vessel (RPV) design and the effect irradiation embrittlement can have, the main degradation mechanism affecting RPVs - Examines embrittlement processes in RPVs in different reactor types, as well as techniques for studying RPV embrittlement

This vital reference is the only one-stop resource on how to assess, prevent, and manage severe nuclear accidents in the light water reactors (LWRs) that pose the most risk to the public. LWRs are the predominant nuclear reactor in use around the world today, and they will continue to be the most frequently utilized in the near future. Therefore, accurate determination of the safety issues associated with such reactors is central to a consideration of the risks and benefits of nuclear power. This book emphasizes the prevention and management of severe accidents to teach nuclear professionals how to mitigate potential risks to the public to the maximum extent possible. - Organizes and presents all the latest thought on LWR nuclear safety in one consolidated volume, provided by the top experts in the field, ensuring high-quality, credible and easily accessible information - Explains how developments in the field of LWR severe accidents have provided more accurate determinations of risk, thereby shedding new light on the debates surrounding nuclear power safety, particularly in light of the recent tragedy in Japan - Concentrates on prevention and management of accidents, developing methodologies to estimate the consequences and associated risks

Chapter 1 - Introduction to Nuclear Reactor Technology Chapter 2 - Nuclear Reactor Physics Chapter 3 - Control Rod Chapter 4 - Generation IV Reactor Chapter 5 - Nuclear Fusion Chapter 6 - Nuclear Fuel Cycle Chapter 7 - Nuclear Safety Chapter 8 - Natural Nuclear Fission Reactor

This book is intended to provide an introduction to the basic principles of nuclear fission reactors for advanced undergraduate or graduate students of physics and engineering. The presentation is also suitable for physicists or engineers who are entering the nuclear power field without previous experience with nuclear reactors. No background knowledge is required beyond that typically acquired in the first two years of an undergraduate program in physics or engineering. Throughout, the emphasis is on explaining why particular reactor systems have evolved in the way they have, without going into great detail about reactor physics or methods of design analysis, which are already covered in a number of excellent specialist texts. The first two chapters serve as an introduction to the basic physics of the atom and the nucleus and to nuclear fission and the nuclear chain reaction. Chapter 3 deals with the fundamentals of nuclear reactor theory, covering neutron slowing down and the spatial dependence of the neutron flux in the reactor, based on the solution of the diffusion equations. The chapter includes a major section on reactor kinetics and control, including'tempera­ ture and void coefficients and xenon poisoning effects in power reactors. Chapter 4 describes various aspects offuel management and fuel cycles, while Chapter 5 considers materials problems for fuel and other constituents of the reactor. The processes of heat generation and removal are covered in Chapter 6.

Chapter 1 - Light Water Reactor Chapter 2 - Boiling Water Reactor Chapter 3 - Pressurized Water Reactor Chapter 4 - Nuclear Fuel Chapter 5 - Neutron Moderator Chapter 6 - Supercritical Water Reactor Chapter 7 - Byron Nuclear Generating Station Chapter 8 - European Pressurized Reactor Chapter 9 - VVER Chapter 10 - CPR-1000s

Chapter 1- Nuclear Reactor Technology Chapter 2 - Advanced Gas-Cooled Reactor Chapter 3 - Boiling Water Reactor Chapter 4 - CANDU Reactor Chapter 5 - Pressurized Water Reactor Chapter 6 - RBMK Chapter 7 - Fast Breeder Reactor Chapter 8 - Breeder Reactor Chapter 9 - Pebble Bed Reactor

Que s'est-il passé le 26 avril 1986 à Tchernobyl? Comment le réacteur N°4, dernier né de la centrale, a-t-il pu s'emballer provoquant la plus grande catastrophe de l'histoire du nucléaire civil? Aurait-on pu éviter cet accident? Quels en ont été les enseignements? Un quart de siècle plus tard, un accident similaire peut-il encore se reproduire? Et Fukushima…? Autour d'une analyse précise de l'accident de Tchernobyl et de ses suites, cet ouvrage présente une analyse générale du contexte énergétique mondial et de ses projections, les aspects physiques et techniques de l'énergie nucléaire, la place qu'elle peut occuper parmi les autres sources d'énergie et les perspectives de son développement. Tchernobyl, 25 ans après... Fukushima. Quel avenir pour le nucléaire? s'adresse à toute personne qui se pose des questions sur ce qu'est l'énergie nucléaire, et qui recherche une information à la fois accessible et précise, en particulier, sur l'accident de Tchernobyl et ses conséquences. Si la lecture de cet ouvrage suppose un minimum de culture scientifique, il n'est toutefois pas destiné spécifiquement aux spécialistes. En particulier, les étudiants, les élus, les citoyens pourront y trouver des réponses simples et claires aux multiples questions qu'ils se posent sur l'utilisation pacifique de l'énergie nucléaire.

This unique volume gives an accurate and very detailed description of the functioning and operation of basic nuclear reactors, as emerging from yet unpublished papers by Nobel Laureate Enrico Fermi.In the first part, the entire course of lectures on Neutron Physics delivered by Fermi at Los Alamos is reported, according to the version made by Anthony P French. Here, the fundamental physical phenomena are described very clearly and comprehensively, giving the appropriate physics grounds for the functioning of nuclear piles. In the second part, all the patents issued by Fermi (and coworkers) on the functioning, construction and operation of several different kinds of nuclear reactors are reported. Here, the main engineering problems are encountered and solved by employing simple and practical methods, which are described in detail.This seminal work mainly caters to students, teachers and researchers working in nuclear physics and engineering, but it is of invaluable interest to historians of physics too, since the material presented here is entirely novel.

This title is the first of four'new-look'books in the Power and Energy series that are aimed at industry professionals rather than academics. Nuclear Power explains in detail how nuclear power works, its costs, its benefits as part of the electricity supply system, and also examines its record.

During the last century, nuclear power has been established as a reliable source of energy in the major industrialised countries. It has recently enjoyed a revival in attention and research due to the environmental concerns surrounding current conventional energy sources. Issues of regulation and safety are at the forefront of all discussions involving nuclear power, and will govern its place in the future. The Future of Nuclear Power takes a technical and comprehensive look at the current and future status of nuclear power throughout the world. The 17 chapters are divided into two main sections: a review of all current generation plants, and concepts for new advanced reactor design and safety. The broad-ranging topics covered by this publication, coupled with the current revival of interest in nuclear energy, make it a timely reference for all nuclear scientists. - Reviews the issues surrounding the future operation of existing commercial nuclear plants - Several chapters dedicated to the extensive research programs in place concerning safe and reliable operation - Compares nuclear and non-nuclear options for energy needs in the future; evaluating the benefits and risks of both

Title from ebook title screen (viewed on Dec. 14, 2004).

Based upon a symposium held at the University of Minnesota, Oct. 10-11, 1969.

'Issued December 1, 1983.'

Nuclear Science and Technology, Volume 10: Variational Methods in Nuclear Reactor Physics presents the mathematical methods of a variational origin that are useful in obtaining approximate solutions to science and engineering problems. This book is composed of five chapters and begins with a discussion on the variation principles for physical systems described by both inhomogeneous and homogeneous equations to develop a generalized perturbation theory. Chapter 2 deals with the applications of variational estimates and generalized perturbation theory to neutron transport problems. Chapter 3 covers the variation principles of the Lagrangian form that are constructed for a general, linear- time-dependent process and for the specific case of the P1 neutron kinetics equations. Chapter 4 presents the general procedure for the variational derivation of synthesis approximations and their applications to problems in reactor physics. This chapter also examines the relationship of the spatial synthesis and finite-element method and a hybrid method that combines features of both methods. Chapter 5 describes the relationship of variation theory with the Hamilton-Jacobi theory and with the optimization theories of the maximum principle and dynamic programming. Nuclear physicists and researchers will find this text invaluable.

Nuclear Science and Technology, Volume 2: Neutron Physics provides information pertinent to neutron and reactor physics. This book presents a discussion of the general area of energy sources, surveying the fusion problem. Organized into 16 chapters, this volume starts with an overview of the broad range of other research related to nuclear technology, radiation effects, solid state work, chemistry, and materials research. This book then examines the experimental data for the cross sections and fission parameters of the fissile nuclides. Other chapters outline the role of fast choppers in time-of-flight spectrometers and consider the total cross section measurements. This book discusses as well the various experiments performed to test the operation of the system. The final chapter deals with the long-range prospects of fusion power. This book is a valuable resource for graduate students, physicists, nuclear engineers, researchers, scientists involved in fusion research will find this book extremely useful.