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Corrosion Issues in Light Water Reactors

Corrosion Issues in Light Water Reactors
  • Author : D Féron,J-M Olive
  • Publisher :Unknown
  • Release Date :2007-06-22
  • Total pages :368
  • ISBN : 9781845693466
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Summary : Stress corrosion cracking is a major problem in light water nuclear reactors, whether pressurised water reactors (PWRs) or boiling water reactors (BWRs). The nuclear industry needs to be able to predict the service life of these power plants and develop appropriate maintenance and repair practices to ensure safe long term operation. This important book sums up key recent research on corrosion in light water reactors and its practical applications. The book is divided into four parts. It begins with an overview of materials degradation due to stress corrosion, corrosion potential monitoring and passivation. Part two summarises research on susceptibility of materials to stress corrosion cracking and the ways it can be initiated. The third part of the book considers stress corrosion crack propagation processes whilst the final part includes practical case studies of corrosion in particular plants. The book reviews corrosion in a range of materials such as low alloy steels, stainless steels and nickel-based alloys. With its distinguished editor and team of contributors, Corrosion issues in light water reactors is a standard work for the nuclear industry. Summarises key recent research on corrosion in light water reactors Includes practical case studies

The Nuclear Fuel of Pressurized Water Reactors and Fast Neutron Reactors

The Nuclear Fuel of Pressurized Water Reactors and Fast Neutron Reactors
  • Author : Henri Bailly,Denise Ménessier,Claude Prunier
  • Publisher :Unknown
  • Release Date :1999-01
  • Total pages :642
  • ISBN : 1898298572
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Summary : This text discusses the design, manufacture and behaviour of nuclear fuel in pressurized water reactors (PWR) and fast reactors (FR). It reflects the knowledge of the French Agency for Nuclear Power (CEA) and other specialized companies in the field.

Safety and Security of Commercial Spent Nuclear Fuel Storage

Safety and Security of Commercial Spent Nuclear Fuel Storage
  • Author : National Research Council,Division on Earth and Life Studies,Board on Radioactive Waste Management,Committee on the Safety and Security of Commercial Spent Nuclear Fuel Storage
  • Publisher :Unknown
  • Release Date :2006-02-19
  • Total pages :126
  • ISBN : 9780309096478
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Summary : In response to a request from Congress, the Nuclear Regulatory Commission and the Department of Homeland Security sponsored a National Academies study to assess the safety and security risks of spent nuclear fuel stored in cooling pools and dry casks at commercial nuclear power plants. The information provided in this book examines the risks of terrorist attacks using these materials for a radiological dispersal device. Safety and Security of Commercial Spent Nuclear Fuel is an unclassified public summary of a more detailed classified book. The book finds that successful terrorist attacks on spent fuel pools, though difficult, are possible. A propagating fire in a pool could release large amounts of radioactive material, but rearranging spent fuel in the pool during storage and providing emergency water spray systems would reduce the likelihood of a propagating fire even under severe damage conditions. The book suggests that additional studies are needed to better understand these risks. Although dry casks have advantages over cooling pools, pools are necessary at all operating nuclear power plants to store at least the recently discharged fuel. The book explains it would be difficult for terrorists to steal enough spent fuel to construct a significant radiological dispersal device.

Dynamics and Control of Nuclear Reactors

Dynamics and Control of Nuclear Reactors
  • Author : Thomas W. Kerlin,Belle R. Upadhyaya
  • Publisher :Unknown
  • Release Date :2019-10-05
  • Total pages :402
  • ISBN : 9780128152621
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Summary : 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

Power Generation Technologies

Power Generation Technologies
  • Author : Paul Breeze
  • Publisher :Unknown
  • Release Date :2005-02-04
  • Total pages :288
  • ISBN : 0080480101
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Summary : This book makes intelligible the wide range of electricity generating technologies available today, as well as some closely allied technologies such as energy storage. The book opens by setting the many power generation technologies in the context of global energy consumption, the development of the electricity generation industry and the economics involved in this sector. A series of chapters are each devoted to assessing the environmental and economic impact of a single technology, including conventional technologies, nuclear and renewable (such as solar, wind and hydropower). The technologies are presented in an easily digestible form. Different power generation technologies have different greenhouse gas emissions and the link between greenhouse gases and global warming is a highly topical environmental and political issue. With developed nations worldwide looking to reduce their emissions of carbon dioxide, it is becoming increasingly important to explore the effectiveness of a mix of energy generation technologies. Power Generation Technologies gives a clear, unbiased review and comparison of the different types of power generation technologies available. In the light of the Kyoto protocol and OSPAR updates, Power Generation Technologies will provide an invaluable reference text for power generation planners, facility managers, consultants, policy makers and economists, as well as students and lecturers of related Engineering courses. · Provides a unique comparison of a wide range of power generation technologies - conventional, nuclear and renewable · Describes the workings and environmental impact of each technology · Evaluates the economic viability of each different power generation system

Stress Corrosion Cracking of Nickel Based Alloys in Water-cooled Nuclear Reactors

Stress Corrosion Cracking of Nickel Based Alloys in Water-cooled Nuclear Reactors
  • Author : Damien Feron,Roger W Staehle
  • Publisher :Unknown
  • Release Date :2016-01-30
  • Total pages :384
  • ISBN : 9780081000625
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Summary : Stress Corrosion Cracking of Nickel Based Alloys in Water-Cooled Nuclear Reactors: The Coriou Effect presents the latest information on brittle failure of metals in corrosive chemical environments under the influence of tensile stresses. Nickel alloys are more resistant to SCC as well as high temperatures and have been widely used in more challenging environments such as nuclear power plants. However, these alloys can suffer SCC under certain conditions, resulting in component failure. A key figure in understanding the mechanisms of SCC in nickel alloys in water-cooled nuclear reactors is Henri Coriou of the CEA, France’s leading center for nuclear research. This book assesses his work in the context of the latest research on SCC in nickel alloys in nuclear power plants. Up-to-date reviews of recent research findings from leading experts in the field Authoritative and comprehensively reviewed by the Working Party 4 on Nuclear Corrosion Showcases the excellent quality and technical accomplishments of Henri Coriou and CEA

How to Drive a Nuclear Reactor

How to Drive a Nuclear Reactor
  • Author : Colin Tucker
  • Publisher :Unknown
  • Release Date :2020-01-25
  • Total pages :264
  • ISBN : 9783030338763
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Summary : Have you ever wondered how a nuclear power station works? This lively book will answer that question. It’ll take you on a journey from the science behind nuclear reactors, through their start-up, operation and shutdown. Along the way it covers a bit of the engineering, reactor history, different kinds of reactors and what can go wrong with them. Much of this is seen from the viewpoint of a trainee operator on a Pressurised Water Reactor - the most common type of nuclear reactor in the world. Colin Tucker has spent the last thirty years keeping reactors safe. Join him on a tour that is the next best thing to driving a nuclear reactor yourself!

Nuclear Power Generation

Nuclear Power Generation
  • Author : P.B. Myerscough
  • Publisher :Unknown
  • Release Date :2013-10-22
  • Total pages :229
  • ISBN : 9780080571195
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Summary : Nuclear power generation has undergone major expansion and developments in recent years; this third edition contains much revised material in presenting the state-of-the-art of nuclear power station designs currently in operation throughout the world. The volume covers nuclear physics and basic technology, nuclear station design, nuclear station operation, and nuclear safety. Each chapter is independent but with the necessary technical overlap to provide a complete work on the safe and economic design and operation of nuclear power stations.

Void Reactivity Effect in Pressurized-water Reactors

Void Reactivity Effect in Pressurized-water Reactors
  • Author : Agència d'Energia Nuclear (Organització de Cooperació i Desenvolupament Econòmic)
  • Publisher :Unknown
  • Release Date :1995
  • Total pages :131
  • ISBN : 9264145915
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Summary :

Nuclear Corrosion Science and Engineering

Nuclear Corrosion Science and Engineering
  • Author : Damien FERON
  • Publisher :Unknown
  • Release Date :2012-02-21
  • Total pages :1072
  • ISBN : 9780857095343
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Summary : Corrosion of nuclear materials, i.e. the interaction between these materials and their environments, is a major issue for plant safety as well as for operation and economic competitiveness. Understanding these corrosion mechanisms, the systems and materials they affect, and the methods to accurately measure their incidence is of critical importance to the nuclear industry. Combining assessment techniques and analytical models into this understanding allows operators to predict the service life of corrosion-affected nuclear plant materials, and to apply the most appropriate maintenance and mitigation options to ensure safe long term operation. This book critically reviews the fundamental corrosion mechanisms that affect nuclear power plants and facilities. Initial sections introduce the complex field of nuclear corrosion science, with detailed chapters on the different types of both aqueous and non aqueous corrosion mechanisms and the nuclear materials susceptible to attack from them. This is complemented by reviews of monitoring and control methodologies, as well as modelling and lifetime prediction approaches. Given that corrosion is an applied science, the final sections review corrosion issues across the range of current and next-generation nuclear reactors, and across such nuclear applications as fuel reprocessing facilities, radioactive waste storage and geological disposal systems. With its distinguished editor and international team of expert contributors, Nuclear corrosion science and engineering is an invaluable reference for nuclear metallurgists, materials scientists and engineers, as well as nuclear facility operators, regulators and consultants, and researchers and academics in this field. Comprehensively reviews the fundamental corrosion mechanisms that affect nuclear power plants and facilities Chapters assess different types of both aqueous and non aqueous corrosion mechanisms and the nuclear materials susceptible to attack from them Considers monitoring and control methodologies, as well as modelling and lifetime prediction approaches

Thermal Analysis of Pressurized Water Reactors

Thermal Analysis of Pressurized Water Reactors
  • Author : Long-sun Tong,Joel Weisman
  • Publisher :Unknown
  • Release Date :1979
  • Total pages :417
  • ISBN : UOM:39015004509132
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Summary :

Materials Ageing and Degradation in Light Water Reactors

Materials Ageing and Degradation in Light Water Reactors
  • Author : K L Murty
  • Publisher :Unknown
  • Release Date :2013-02-18
  • Total pages :440
  • ISBN : 9780857097453
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Summary : Light water reactors (LWRs) are the predominant class of nuclear power reactors in operation today; however, ageing and degradation can influence both their performance and lifetime. Knowledge of these factors is therefore critical to safe, continuous operation. Materials ageing and degradation in light water reactors provides a comprehensive guide to prevalent deterioration mechanisms, and the approaches used to handle their effects. Part one introduces fundamental ageing issues and degradation mechanisms. Beginning with an overview of ageing and degradation issues in LWRs, the book goes on to discuss corrosion in pressurized water reactors and creep deformation of materials in LWRs. Part two then considers materials’ ageing and degradation in specific LWR components. Applications of zirconium alloys in LWRs are discussed, along with the ageing of electric cables. Materials management strategies for LWRs are then the focus of part three. Materials management strategies for pressurized water reactors and VVER reactors are considered before the book concludes with a discussion of materials-related problems faced by LWR operators and corresponding research needs. With its distinguished editor and international team of expert contributors, Materials ageing and degradation in light water reactors is an authoritative review for anyone requiring an understanding of the performance and durability of this type of nuclear power plant, including plant operators and managers, nuclear metallurgists, governmental and regulatory safety bodies, and researchers, scientists and academics working in this area. Introduces the fundamental ageing issues and degradation mechanisms associated with this class of nuclear power reactors Considers materials ageing and degradation in specific light water reactor components, including properties, performance and inspection Chapters also focus on material management strategies

Nuclear Corrosion

Nuclear Corrosion
  • Author : Stefan Ritter
  • Publisher :Unknown
  • Release Date :2020-08-28
  • Total pages :496
  • ISBN : 9780128237205
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Summary : Nuclear Corrosion: Research, Progress and Challenges, part of the “Green Book series of the EFC, builds upon the foundations of the very first book published in this series in 1989 (“Number 1 - Corrosion in the Nuclear Industry ). This newest volume provides an overview on state-of-the-art research in some of the most important areas of nuclear corrosion. Chapters covered include aging phenomena in light water reactors, reprocessing plants, nuclear waste disposal, and supercritical water and liquid metal systems. This book will be a vital resource for both researchers and engineers working within the nuclear field in both academic and industrial environments. Discusses industry related aspects of materials in nuclear power generation and how these materials react with the environment Provides comprehensive coverage of the topic as written by noted experts in the field Includes coverage of nuclear waste corrosion

Pressurised Water Reactor Main Steam Line Break (MSLB) Benchmark: Results of phase I on point kinetics

Pressurised Water Reactor Main Steam Line Break (MSLB) Benchmark: Results of phase I on point kinetics
  • Author : B. Taylor,K. Ivanov
  • Publisher :Unknown
  • Release Date :2000
  • Total pages :136
  • ISBN : 9264182802
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Summary :

Intelligent Manufacturing and Mechatronics

Intelligent Manufacturing and Mechatronics
  • Author : Zamberi Jamaludin,Mohd Najib Ali Mokhtar
  • Publisher :Unknown
  • Release Date :2019-08-29
  • Total pages :601
  • ISBN : 9789811395390
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Summary : This book presents the proceedings of SympoSIMM 2019, the 2nd edition of the Symposium on Intelligent Manufacturing and Mechatronics. Focusing on “Strengthening Innovations Towards Industry 4.0”, the book presents studies on the details of Industry 4.0’s current trends. Divided into five parts covering various areas of manufacturing engineering and mechatronics stream, namely, artificial intelligence, instrumentation and controls, intelligent manufacturing, modelling and simulation, and robotics., the book is a valuable resource for readers wishing to embrace the new era of Industry 4.0.

Understanding and Mitigating Ageing in Nuclear Power Plants

Understanding and Mitigating Ageing in Nuclear Power Plants
  • Author : Philip G Tipping
  • Publisher :Unknown
  • Release Date :2010-10-26
  • Total pages :944
  • ISBN : 9781845699956
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Summary : Plant life management (PLiM) is a methodology focussed on the safety-first management of nuclear power plants over their entire lifetime. It incorporates and builds upon the usual periodic safety reviews and licence renewals as part of an overall framework designed to assist plant operators and regulators in assessing the operating conditions of a nuclear power plant, and establishing the technical and economic requirements for safe, long-term operation. Understanding and mitigating ageing in nuclear power plants critically reviews the fundamental ageing-degradation mechanisms of materials used in nuclear power plant structures, systems and components (SSC), along with their relevant analysis and mitigation paths, as well as reactor-type specific PLiM practices. Obsolescence and other less obvious ageing-related aspects in nuclear power plant operation are also examined in depth. Part one introduces the reader to the role of nuclear power in the global energy mix, and the importance and relevance of plant life management for the safety regulation and economics of nuclear power plants. Key ageing degradation mechanisms and their effects in nuclear power plant systems, structures and components are reviewed in part two, along with routes taken to characterise and analyse the ageing of materials and to mitigate or eliminate ageing degradation effects. Part three reviews analysis, monitoring and modelling techniques applicable to the study of nuclear power plant materials, as well as the application of advanced systems, structures and components in nuclear power plants. Finally, Part IV reviews the particular ageing degradation issues, plant designs, and application of plant life management (PLiM) practices in a range of commercial nuclear reactor types. With its distinguished international team of contributors, Understanding and mitigating ageing in nuclear power plants is a standard reference for all nuclear plant designers, operators, and nuclear safety and materials professionals and researchers. Introduces the reader to the role of nuclear power in the global energy mix Reviews the fundamental ageing-degradation mechanisms of materials used in nuclear power plant structures, systems and components (SSC) Examines topics including elimination of ageing effects, plant design, and the application of plant life management (PLiM) practices in a range of commercial nuclear reactor types

Nuclear Fission Reactors

Nuclear Fission Reactors
  • Author : I. R. Cameron
  • Publisher :Unknown
  • Release Date :2012-12-06
  • Total pages :398
  • ISBN : 9781461335276
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Summary : 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.

Water Chemistry of Nuclear Reactor Systems 7

Water Chemistry of Nuclear Reactor Systems 7
  • Author : Anonim
  • Publisher :Unknown
  • Release Date :1996
  • Total pages :440
  • ISBN : 0727725653
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Summary : These proceedings of the seventh conference address the chemical factors important to the operation of water power reactors with minimum corrosion, operator radiation dose and effluent discharges.

Global Applications of the Asme Boiler & Pressure Vessel Code

Global Applications of the Asme Boiler & Pressure Vessel Code
  • Author : K. R. Rao
  • Publisher :Unknown
  • Release Date :2016
  • Total pages :500
  • ISBN : 0791861074
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Summary : his publication follows the phenomenal success of not only the four editions of the Companion Guide to the ASME Boiler & Pressure Vessel Code published by ASME Press, but also two related updated volumes. Thus, this is the third book that is also a "standalone-publication," addressing Global Applications of the ASME B&PV Code. This book not only updates information of 16 chapters of the third volume of the third edition of the Companion Guide, but has additional 5 chapters selected for their unique features of ASME Boiler and Pressure Vessel Codes used internationally. This book has five parts addressing Global Applications of ASME B&PV Codes and Standards: Part 1: North America and Western Europe which includes Canada, France, UK, Belgium, Germany, Spain and Finland in addition to the Pressure Equipment Directive of the European Union Countries. Part 2: Central and Eastern Europe includes Russian, Czech and Slovakian Codes and Hungary. Part 3: South Africa. Part 4: Asia including Japan, Korea, Taiwan, India and China. Part 5: Special Topics is addressed by ASME Code experts to cover in four chapters: (i) Global Harmonization of Nuclear Codes and Standards; (ii) Global Flaw Modelling Characteristics; (iii) AREVA's perspective of spent fuel storage in a "A Case Study of Dry Storage System for Used Nuclear Fuel; and finally in last chapter (iv) Has three parts in "Utilities' perspective of spent fuel storage" - the first one is covers ENTERGY, the second part Pacific Gas and Electric (PG&E) and the last part has Ontario Hydro's experiences. Thus different perspectives of the Spent Fuel Storage which are critical to the continuation of nuclear industry are addressed by various experts in this chapter.

Single-phase, Two-phase and Supercritical Natural Circulation Systems

Single-phase, Two-phase and Supercritical Natural Circulation Systems
  • Author : Pallippattu Krishnan Vijayan,Arun K. Nayak,Naveen Kumar
  • Publisher :Unknown
  • Release Date :2019-06-19
  • Total pages :650
  • ISBN : 9780081024874
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Summary : Single-Phase, Two-Phase and Supercritical Natural Circulation Systems provides readers with a deep understanding of natural circulation systems. This book equips the reader with an understanding on how to detect unstable loops to ensure plant safety and reliability, calculate heat transport capabilities, and design effective natural circulation loops, stability maps and parallel channel systems. Each chapter begins with an introduction to the circulation system before discussing each element in detail and analyzing its effect on the performance of the system. The book also presents thermosyphon heat transport devices in nuclear and other industrial plants, a common information need for students and researchers alike. This book is invaluable for engineers, designers, operators and consultants in nuclear, mechanical, electrical and chemical disciplines. Presents single-phase, two-phase and supercritical natural circulation systems together in one resource to fill an existing knowledge gap Guides the reader through relevant processes, such as designing, analyzing and generating stability maps and natural circulation loops, calculating heat transport capabilities, and maintaining natural circulation system operations Includes global case studies and examples to increase understanding, along with important IAEA standards and procedures

Design and Construction of Nuclear Power Plants

Design and Construction of Nuclear Power Plants
  • Author : Rüdiger Meiswinkel,Julian Meyer,Jürgen Schnell
  • Publisher :Unknown
  • Release Date :2013-04-10
  • Total pages :150
  • ISBN : 9783433602751
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Summary : Despite all the efforts being put into expanding renewable energy sources, large-scale power stations will be essential as part of a reliable energy supply strategy for a longer period. Given that they are low on CO2 emissions, many countries are moving into or expanding nuclear energy to cover their baseload supply. Building structures required for nuclear plants whose protective function means they are classified as safety-related, have to meet particular construction requirements more stringent than those involved in conventional construction. This book gives a comprehensive overview from approval aspects given by nuclear and construction law, with special attention to the interface between plant and construction engineering, to a building structure classification. All life cycle phases are considered, with the primary focus on execution. Accidental actions on structures, the safety concept and design and fastening systems are exposed to a particular treatment. Selected chapters from the German concrete yearbook are now being published in the new English "Beton-Kalender Series" for the benefit of an international audience. Since it was founded in 1906, the Ernst & Sohn "Beton-Kalender" has been supporting developments in reinforced and prestressed concrete. The aim was to publish a yearbook to reflect progress in "ferro-concrete" structures until - as the book's first editor, Fritz von Emperger (1862-1942), expressed it - the "tempestuous development" in this form of construction came to an end. However, the "Beton-Kalender" quickly became the chosen work of reference for civil and structural engineers, and apart from the years 1945-1950 has been published annually ever since.