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Books > Professional & Technical > Energy technology & engineering > Nuclear power & engineering
Researchers in plasma fusion labs; also graduate students in plasma physics, high-energy physics, and libraries
This revised book covers the fundamentals of thermodynamics required to understand electrical power generation systems, honing in on the application of these principles to nuclear reactor power systems. This text treats the fundamentals of thermodynamics from the perspective of nuclear power systems. In addition to the Four Laws of Thermodynamics, it discusses Brayton and Rankine power cycles in detail with an emphasis on how they are implemented in nuclear systems. Chapters have been brought up-to-date due to significant new results that have become available for intercooled systems and combined cycles and include an updated steam table. The book starts with basic principles of thermodynamics as applied to power plant systems. It then describes how Nuclear Air-Brayton systems will work. It documents how they can be designed and the expected ultimate performance. It describes several types of Nuclear Air-Brayton systems that can be employed to meet different requirements and estimates component sizes and performance criteria for Small Modular Reactors (SMR) based on the Air-Brayton concept. The book provides useful insight into the engineering of nuclear power systems for students and the tabular data will be of great use to practicing engineers.
This book introduces the reader to the use of Monte Carlo methods for solving practical problems in radiation transport, and will also serve as a reference work for practitioners in the field. It assumes the reader has a general knowledge of calculus and radiation physics, and a knowledge of Fortran programming, but assumes no prior knowledge of stochastic methods or statistical physics. The subject is presented by a combination of theoretical development and practical calculations. Because Monte Carlo methods are closely linked to the use of computers, from the beginning the reader is taught to convert the theoretical constructs developed in the text into functional software for use on a personal computer. Example problems provide the reader with an in-depth understanding of the concepts presented and lead to the production of a unique learning tool, a probabilistic framework code that models in a simple manner the features of production of Monte Carlo transport codes. This framework code is developed in stages such that every function is understood, tested, and demonstrated - random sampling, generating random numbers, implementing geometric models, using variance reduction, tracking particles in a random walk, testing the thoroughness with which the problem phase space is sampled, scoring detectors, and obtaining estimates of uncertainty in results. Advanced topics covered include criticality, correlated sampling, adjoint transport, and neutron thermalization. Monte Carlo codes can produce highly precise wrong answers. The probability of this occurring is increased if production codes are run as opaque, black boxes' of software. This text attempts to make Monte Carlo into acomprehensible, usable tool for solving practical transport problems. It is suitable for advanced undergraduate and graduate students and researchers who wish to expand their knowledge of the Monte Carlo technique.
Fuzzy systems and soft computing are new computing techniques that are tolerant to imprecision, uncertainty and partial truths. Applications of these techniques in nuclear engineering present a tremendous challenge due to its strict nuclear safety regulation. The fields of nuclear engineering, fuzzy systems and soft computing have nevertheless matured considerably during the last decade. This book presents new application potentials for Fuzzy Systems and Soft Computing in Nuclear Engineering. The root of this book can be traced back to the series of the first, second and third international workshops on Fuzzy Logic and Intelligent Technologies in Nuclear Science (FUNS), which were successfully held in Mol, September 14-16, 1994 (FLINS'94), in Mol, September 25-27, 1996 (FLINS'96), and in Antwerp, September 14-16, 1998 (FLINS'98). The conferences were organised by the Belgian Nuclear Research Centre (SCKeCEN) and aimed at bringing together scientists, researchers, and engineers from academia and industry, at introducing the principles of fuzzy logic, neural networks, genetic algorithms and other soft computing methodologies, to the field of nuclear engineering, and at applying these techniques to complex problem solving within nuclear industry and related research fields. This book, as its title suggests, consists of nuclear engineering applications of fuzzy systems (Chapters 1-10) and soft computing (Chapters 11-21). Nine pertinent chapters are based on the extended version of papers at FLINS'98 and the other 12 chapters are original contributions with up-to-date coverage of fuzzy and soft computing applications by leading researchers written exclusively for this book."
This edited book is directed primarily to the discussion of the most recent developments and on-going research related to all areas pertaining to plant surveillance and diagnosis. The secondary aim of this book is to identify the successful applications of already well-settled methodological tools in the field. It will highlight advantages of intelligent systems, AI techniques, and integration of soft computing tools and traditional tools, for a better service in all aspects related to power plant surveillance and diagnostics. It also reports recent research results and provides a state of the art on AI in power plant surveillance and diagnostics. The book especially focuses on theoretical and analytical solutions to the problems of real interest in AI techniques, possibly combined with other traditional computing tools.
Atomic Information Technology revaluates current conceptions of the information technology aspects of the nuclear industry. Economic and safety research in the nuclear energy sector are explored, considering statistical methods which incorporate Monte-Carlo simulations for practical applications. Divided into three sections, Atomic Information Technology covers: Atomic economics and management, Atomic safety and reliability, and Atomic safeguarding and security. Either as a standalone volume or as a companion to conventional nuclear safety and reliability books, Atomic Information Technology acts as a concise and thorough reference on statistical assessment technology in the nuclear industry. Students and industry professionals alike will find this a key tool in expanding and updating their understanding of this industry and the applications of information technology within it.
This monograph recounts and details the development of a nuclear rocket engine reactor (NRER). In particular, it explains the working capacity of an active zone NRER under mechanical and thermal load, intensive neutron fluxes, and high-energy generation (up to 30 MBT/l) in a working medium (hydrogen) at temperatures up to 3100 K. The design principles and bearing capacity of reactors area discussed on the basis of simulation experiments and test data of a prototype reactor. Property data of dense constructional, porous thermal insulating and fuel materials such as carbide and uranium carbide compounds in the temperatures interval 300 - 3000 K are presented.; technological aspects of strength and thermal strength resistance of materials are also considered. As well, a procedure to design possible emergency processes in the NRER is developed and risks for their origination are evaluated. Finally, prospects for use in pilotless space devices and piloted interplanetary ships are reviewed.
This book, comprising contributions presented at the XIX Edoardo Amaldi Conference, examines important aspects of international cooperation aimed at enhancing nuclear safety, security, safeguards (the "3S"), and non-proliferation, thereby assisting in the development and maintenance of the verification regime and progress toward a nuclear weapon-free world. The Conference served as a forum where eminent scientists, diplomats, and policymakers could compare national perspectives and update international collaborations. The book opens by addressing the political, institutional, and legal dimensions of the 3S and non-proliferation; current challenges are discussed and attempts made to identify possible solutions and future improvements. Subsequent sections consider scientific developments that can contribute to increased effectiveness in the implementation of international regimes, particularly in critical areas, technology foresight, and the ongoing evaluation of current capabilities. The closing sections discuss scientific and technical challenges to the effective implementation of the 3S approach and the role of international cooperation and scientific community actions in leading the world toward peace and security.
During the past century, world-wide energy consumption has risen dramatically, which leads to a quest for new energy sources. Fusion of hydrogen atoms in hot plasmas is an attractive approach to solve the energy problem, with abundant fuel, inherent safety and no long-lived radioactivity. However, one of the limits on plasma performance is due to the various classes of magneto-hydrodynamic instabilities that may occur. The physics and control of these instabilities in modern magnetic confinement fusion devices is the subject of this book. Written by foremost experts, the contributions will provide valuable reference and up-to-date research reviews for "old hands" and newcomers alike.
As a flexible, cost-effective energy alternative to large scale nuclear power reactors, this book examines the potential future use of small modular reactors for the generation of electricity in different regions. Exploring advanced nuclear technologies, chapters describe the current situation and perspective of the small modular reactors market (SMRs) in different regions around the word, including North and South America, Europe, Asia, Middle East and Africa. Particular attention is paid to the benefits of using these types of reactors for the generation of electricity, discussing their efficiency and reduced construction time, as well as exploring the main difficulties encountered in the development stage. Looking at the potential dangers that SMRs pose to the environment and population, the text presents the new safety measures that have been adopted in SMRs design to reduce future risk.
This book is a compilation of selected papers from the 3rd International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plants, held in Harbin, China on 15th-17th August 2018. The symposium discussed the status quo, technical advances and development direction of digital instrument control technology, software reliability, information security and physical protection in the process of nuclear power development. Offering technical insights and know from leading experts, this book 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.
This thesis deals with the problem of ion confinement in thermonuclear fusion devices. It is a topic of general interest, as it helps to understand via numerical simulations the ion confinement properties in complex geometries, in order to predict their behavior and maximize the performance of future fusion reactors. The main work carried out in this thesis is the improvement and exploitation of an existing simulation code called ISDEP. This code solves the so-called ion collisional transport in arbitrary plasma geometry, improving in this sense other existing codes. Additionally, it presents outstanding portability and scalability in distributed computing architectures, such as Grid or Volunteer Computing. The main physical results can be divided into two blocks. First, the study of 3D ion transport in ITER is presented. ITER is the largest fusion reactor (under construction) and most of the simulations so far assume the axis-symmetry of the device. Unfortunately, this symmetry is only an approximation because of the discrete number of magnetic coils used. ISDEP has shown, using a simple model of the 3D magnetic field, how the ion confinement is affected by this symmetry breaking. Secondly, ISDEP has been applied successfully to the study of fast ion dynamics in fusion plasmas. The fast ions, with energies much larger than the thermal energy, are a product of the device's heating system. Thus, a numerical predictive tool can be used to improve the heating efficiency. ISDEP has been combined with the FAFNER2 code to study such ions in stellarator (TJ-II, LHD) and tokamak (ITER) geometries. It has also been validated by experimental results. In particular, comparisons with the CNPA diagnostic in the TJ-II stellarator are remarkable.
This book examines the different spatial control techniques for regulation of spatial power distribution in advanced heavy water reactors (AHWR). It begins with a review of the literature pertinent to the modeling and control of large reactors. It also offers a nodal-core model based on finite difference approximation since the AHWR core is considered to be divided into 17 relatively large nodes. Further, it introduces a nonlinear model characterizing important thermal hydraulics parameters of AHWR and integrates it into the neutronics model to obtain a coupled neutronics-thermal hydraulics model of AHWR. The book also presents a vectorized nonlinear model of AHWR and implements it in MATLAB/Simulink environment. The model of the reactor is then linearized at the rated power and put into standard state variable form. It is characterized by 90 states, 5 inputs and 18 outputs. Lastly, it discusses control techniques for a nonlinear model of AHWR. This book will prove to be a valuable resource for professional engineers and implementation specialists, researchers and students.
Separation technologies are of crucial importance to the goal of significantly reducing the volume of high-level nuclear waste, thereby reducing the long-term health risks to mankind. International co-operation, including the sharing of concepts and methods, as well as technology transfer, is essential in accelerating research and development in the field. The writers of this book are all internationally recognised experts in the field of separation technology, well qualified to assess and criticize the current state of separation research as well as to identify future opportunities for the application of separation technologies to the solution of nuclear waste management problems. The major emphases in the book are research opportunities in the utilization of innovative and potentially more efficient and cost effective processes for waste processing/treatment, actinide speciation/separation methods, technological processing, and environmental restoration.
Civil engineering has an important part to play at every stage of the nuclear fuel cycle - from the choice of site and conception of the design of a major power station or fuel plan through modifications during operations, to the final stages of designing and building waste management stores and repositories. Technical demands on designers and builders of nuclear plants are ever increasing and together with ever greater safety requirements the designer has to consider natural and man-made disasters. Inevitably increased safety and quality standards result in increased costs. This book examines ways in which the industry has responded to this challenge with new methods of construction giving higher productivity and faster construction times.
This book of proceedings collects the papers presented at the workshop on "Diagnostics for Experimental Fusion Reactors" held at Villa Monastero, Varenna (Italy) September 4-12, 1997. This workshop was the seventh organized by the International School of Plasma Physics "Piero Caldirola" on the topic of plasma diagnostics and the second devoted to the diagnostic studies for the International Thermonuclear Experimental Reactor (ITER). The proceedings of the first workshop on ITER diagnostics were published by Plenum Press in 1996 with the title "Diagnostics for Experimental Thermonuclear Fusion Reactors." While many of the ideas and studies reported in the first workshop remain valid, there has been sub stantial progress in the design and specification of many diagnostics for ITER. This moti vated a second workshop on this topic and the publication of a new book of proceedings. ITER is a joint venture between Europe, Japan, Russia and USA in the field of con trolled thermonuclear fusion research. The present aim of ITER is to design an experimental fusion reactor that can demonstrate ignition and sustained burn in a magnetically confined plasma. To achieve this goal, a wide range of plasma parameters will have to be measured reliably. It is also anticipated that diagnostics will be used much more extensively as input to control systems on ITER than on present fusion devices and this will require increased relia bility and long-term stability."
In September, 1999, with the generous support of NATO, scientists from 18 different nations gathered in Katsiveli, Yalta, Ukraine at the NATO Advanced Research Workshop on Hydrogen Materials Science and Chemistry of Metal Hydrides to present their research and to discuss world energy problems and possible solutions, interactions of hydrogen with materials, the role of hydrogen in materials science, and the chemistry of metal hydrides. High level and highly professional presentations were accompanied by a great deal of discussion and debate of the issues from both fundamental and global perspectives. The result was a large number of new collaborations, new directions, and better understanding of energy and materials issues. The research presented at this meeting can be found in this volume. These papers range from global perspectives such as the new vision of energy and how hydrogen fits into that future, to reviews such as a look at nickel hydride over the last 40 years, to very specific current research. A large number of papers are included on hydrogen and materials. These papers include articles on properties such as superconductivity, diffusion EMF, magnetic properties, physico chemical properties, phase composition, and permeability as a result of the interaction with or incorporation of hydrogen. Also included are papers discussing the use of hydrogen as a processing or alloying agent. The use of hydrogen in the synthesis of battery electrode materials, composite materials, and alloys is also presented."
Safety of VVER-440 Reactors endeavours to promote an increase in the safety of VVER-440 nuclear reactors via the improvement of fission products limitation systems and the implementation of special non-destructive spectroscopic methods for materials testing. All theoretical and experimental studies performed the by author over the last 25 years have been undertaken with the aim of improving VVER-440 defence in depth, which is one of the most important principle for ensuring safety in nuclear power plants. Safety of VVER-440 Reactors is focused on the barrier system through which the safety principle is organised: * nuclear fuel matrix; * fuel cladding; * integrity of primary circuit; and * confinement system. All these barriers are described in detail and are compared to European standards. Industrial engineers will find Safety of VVER-440 Reactors a useful guide to the safe operation of nuclear power plants and it is an informative source of information for researchers in both industry and academia. Employees of related governmental and regulatory organisations may also benefit from reading this book.
Market: Scientists and students involved in thermonuclear fusion research. Thermonuclear fusion research using the confinement device tokamak represents one of the most prominent science projects in the second half of the 20th century. International Tokamak Community is now committing significant effort and funds to experiments with burning plasma, hot and dense enough to produce significant nuclear fusion reactions. The methods used to enhance tokamak performance have a profound and immediate effect on machine design. This book provides an up-to-date account of research in tokamak fusion and puts forward innovative ideas in confinement physics.
While many books are available on disaster medicine, none is specifically devoted to the role of physicians in the management of patients exposed to radiation leakage from a damaged nuclear power plant. "Radiation Disaster Medicine" aims to fill this void based on the response to the Fukushima nuclear accident. Each chapter addresses principles and practices of radiation medicine within the specific context of that accident. Topics covered include the role of physicians in radiation disasters, the concepts of external and internal exposure, prehospital and hospital response, disaster behavioral health, and radiation emergency response from the perspective of national and international institutions. Most of the contributors are active educators and researchers in radiation medicine with first-hand experience in dealing with prehospital triage and management of patients within secondary and tertiary care hospitals in Japan.
From the multi-award winning editorial team of G. Robert Odette (UCSB) and Steve Zinkle (ORNL), and with a contributor board drawn exclusively from the leaders of each alloy discipline, "Structural Alloys for Nuclear Energy Applications" instructs the current and next generations of researchers and industry staff on the behavior of steels and nickel-base alloys for nuclear energy applications. The book covers phenomenon including fatigue, deformation, and embrittlement, as well as materials topics such as advanced ODS steels, RAFM steels for fusion, computational design of nuclear structural materials, and much more. Distilling valuable archival information for international
researchers in the field of radiation effects on structural
materials, this full-color reference is a critical resource for
graduate students and institutional staff at this time of pivotal
change in the nuclear industry.
This book presents a comprehensive overview of Ukraine's nuclear history, beginning from its experiences within the Russian Empire in the early 20th century, through the Soviet period, to the emergence of Ukraine as an independent state that inherited the world's third-largest nuclear arsenal. The book discusses the development of the nuclear infrastructure on Ukrainian soil and offers a rich and nuanced background of how Ukraine became an important and integrated part of the Soviet nuclear infrastructure. It further analyzes Ukraine's nuclear disarmament based on extensive primary source material and places the Ukrainian nuclear reversal process in a larger international political context where Russias, the United States, and other players actions are interpreted in the light of the impact on the current nuclear non-proliferation regime. Finally, the book presents the nuclear-related development after the nuclear disarmament. It describes the integration of Ukraine into the international community and the role of nuclear power in the energy mix of the nation today. Concluding, Ukraines adaptation to the new security situation after the Russian annexation of Crimea is described and discussed. This volume is a must-read for scholars, researchers, students, and policy-makers interested in a better understanding of Ukraine's nuclear history, the political background of the conflict in Eastern Ukraine, as well as of security studies and international relations in general. The work on this book has been supported by the Swedish Radiation Authority (SSM) in the Nuclear History of Ukraine Project (2015-2019). |
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