Management Of Ageing In Graphite Reactor Cores
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Management Of Ageing In Graphite Reactor Cores
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Author : Gareth B. Neighbour
language : en
Publisher: Royal Society of Chemistry
Release Date : 2007
Management Of Ageing In Graphite Reactor Cores written by Gareth B. Neighbour and has been published by Royal Society of Chemistry this book supported file pdf, txt, epub, kindle and other format this book has been release on 2007 with Nature categories.
This product is not available separately, it is only sold as part of a set. There are 750 products in the set and these are all sold as one entity. This product is not available separately, it is only sold as part of a set. There are 750 products in the set and these are all sold as one entity.
Securing The Safe Performance Of Graphite Reactor Cores
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Author : Gareth B. Neighbour
language : en
Publisher: Royal Society of Chemistry
Release Date : 2010
Securing The Safe Performance Of Graphite Reactor Cores written by Gareth B. Neighbour and has been published by Royal Society of Chemistry this book supported file pdf, txt, epub, kindle and other format this book has been release on 2010 with Science categories.
A comprehensive and up-to-date account of recent advances in securing safe performance of graphite-moderated nuclear reactors both within the UK and abroad.
Understanding And Mitigating Ageing In Nuclear Power Plants
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Author : Philip G Tipping
language : en
Publisher: Elsevier
Release Date : 2010-10-26
Understanding And Mitigating Ageing In Nuclear Power Plants written by Philip G Tipping and has been published by Elsevier this book supported file pdf, txt, epub, kindle and other format this book has been release on 2010-10-26 with Technology & Engineering categories.
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
Modelling And Measuring Reactor Core Graphite Properties And Performance
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Author : Gareth B. Neighbour
language : en
Publisher: Royal Society of Chemistry
Release Date : 2012
Modelling And Measuring Reactor Core Graphite Properties And Performance written by Gareth B. Neighbour and has been published by Royal Society of Chemistry this book supported file pdf, txt, epub, kindle and other format this book has been release on 2012 with Nature categories.
Gas-cooled, graphite-moderated nuclear reactors suffer ageing and degradation to the graphite during service posing a threat to the functionality of the core, and potentially, the safe operation of the reactor. Thus, the importance of modelling and measuring reactor core graphite properties and performance increases especially as continued use beyond the designed life time becomes significant. This book captures the proceedings from the third in a series of meetings addressing the extensive research and analysis performed to ensure the continuing safe performance of the graphite cores. Covering four broad themes: mechanistic; statistical; empirical; and, plant performance, this book should appeal to a broad range of readers from engineers and reactor operators to policy makers.
Carbon Materials Science And Applications
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Author : Chung Deborah D L
language : en
Publisher: World Scientific
Release Date : 2019-01-18
Carbon Materials Science And Applications written by Chung Deborah D L and has been published by World Scientific this book supported file pdf, txt, epub, kindle and other format this book has been release on 2019-01-18 with Technology & Engineering categories.
Elemental carbon materials take numerous forms including graphite, carbon fiber, carbon nanotube, graphene, carbon black, activated carbon, fullerene and diamond. These forms differ greatly in the structure, properties, fabrication method, and applications. The applications of these carbon forms include electronic, electromagnetic, electrochemical, environmental and biomedical applications. Carbon materials are a subject of intense research, with strong relevance to both science and technology.This book provides a tutorial-style and up-to-date coverage of the carbon forms. In addition to an introductory chapter on carbon materials, the book includes chapters on graphite, graphene, carbon black, activated carbon, carbon fibers, and carbon nanofibers/nanotubes. For example, the chapter on graphite covers various materials in the graphite family, including polycrystalline graphite, pyrolytic graphite, turbostratic carbon, intercalated graphite, graphite oxide, exfoliated graphite and flexible graphite, in addition to their electronic and mechanical properties.This book is suitable for use as a textbook for undergraduate and graduate students in science and engineering, and as a reference book for professionals. It is dedicated to the memory of the author's PhD thesis advisor, Professor M S Dresselhaus (1930-2017) of Massachusetts Institute of Technology.
Nuclear Reactor Engineering Principle And Concepts
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Author : Vaidyanathan G.
language : en
Publisher: S. Chand Publishing
Release Date : 2013
Nuclear Reactor Engineering Principle And Concepts written by Vaidyanathan G. and has been published by S. Chand Publishing this book supported file pdf, txt, epub, kindle and other format this book has been release on 2013 with Technology & Engineering categories.
The book exposes the student to the various facets of nuclear fuel cycle right from mining to waste disposal.It introduces the student to the heat transfer and fluid flow processes in different types of reactors viz. Pressurized Water Reactor, Pressurized Heavy Water Reactor, Boiling Water Reactor, Gas Cooled Reactors and Fast Reactors besides aspects of nuclear safety.To help the student in better understanding Figures and Tables have been provided at various places in the text.
Electromagnetic Nondestructive Evaluation Xx
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Author : H.G. Ramos
language : en
Publisher: IOS Press
Release Date : 2017-06-02
Electromagnetic Nondestructive Evaluation Xx written by H.G. Ramos and has been published by IOS Press this book supported file pdf, txt, epub, kindle and other format this book has been release on 2017-06-02 with Science categories.
Electromagnetic Nondestructive Evaluation (ENDE) provides an important method for assessing the condition of objects by observing the electromagnetic response to electric currents and/or magnetic fields introduced within them. Because it does not permanently alter the objects being tested, it is an invaluable tool for product evaluation, troubleshooting and research, and is employed in many fields from engineering and medicine to art. This volume presents selected papers from the International Workshop on Electromagnetic Nondestructive Evaluation (ENDE2016), held in Lisbon, Portugal, in September 2016. This 21st edition of the workshop focused on the theoretical and application research into methods of electromagnetic non-destructive evaluation and, like previous editions, provided a forum for exchanging ideas and discussing recent developments. The book is divided into 6 sections which cover advanced ENDE sensors; material characterization; new developments; analytical and numerical modeling; inverse problems; signal processing; monitoring and diagnosis of mechanical structures; and innovative industrial applications of ENDE. Providing an overview of recent research and developments in the field, the book will be of interest to all those involved in ENDE research or applying it in their work.
Comprehensive Nuclear Materials
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Author :
language : en
Publisher: Elsevier
Release Date : 2020-07-22
Comprehensive Nuclear Materials written by and has been published by Elsevier this book supported file pdf, txt, epub, kindle and other format this book has been release on 2020-07-22 with Science categories.
Materials in a nuclear environment are exposed to extreme conditions of radiation, temperature and/or corrosion, and in many cases the combination of these makes the material behavior very different from conventional materials. This is evident for the four major technological challenges the nuclear technology domain is facing currently: (i) long-term operation of existing Generation II nuclear power plants, (ii) the design of the next generation reactors (Generation IV), (iii) the construction of the ITER fusion reactor in Cadarache (France), (iv) and the intermediate and final disposal of nuclear waste. In order to address these challenges, engineers and designers need to know the properties of a wide variety of materials under these conditions and to understand the underlying processes affecting changes in their behavior, in order to assess their performance and to determine the limits of operation. Comprehensive Nuclear Materials, Second Edition, Seven Volume Set provides broad ranging, validated summaries of all the major topics in the field of nuclear material research for fission as well as fusion reactor systems. Attention is given to the fundamental scientific aspects of nuclear materials: fuel and structural materials for fission reactors, waste materials, and materials for fusion reactors. The articles are written at a level that allows undergraduate students to understand the material, while providing active researchers with a ready reference resource of information. Most of the chapters from the first Edition have been revised and updated and a significant number of new topics are covered in completely new material. During the ten years between the two editions, the challenge for applications of nuclear materials has been significantly impacted by world events, public awareness, and technological innovation. Materials play a key role as enablers of new technologies, and we trust that this new edition of Comprehensive Nuclear Materials has captured the key recent developments. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environments Comprehensive resource for up-to-date and authoritative information which is not always available elsewhere, even in journals Provides an in-depth treatment of materials modeling and simulation, with a specific focus on nuclear issues Serves as an excellent entry point for students and researchers new to the field
Graphite Materials Testing In The Atr For Lifetime Management Of Magnox Reactors
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Author :
language : en
Publisher:
Release Date : 2002
Graphite Materials Testing In The Atr For Lifetime Management Of Magnox Reactors written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2002 with categories.
A major feature of the Magnox gas cooled reactor design is the graphite core, which acts as the moderator but also provides the physical structure for fuel, control rods, instrumentation and coolant gas channels. The lifetime of a graphite core is dependent upon two principal aging processes: irradiation damage and radiolytic oxidation. Irradiation damage from fast neutrons creates lattice defects leading to changes in physical and mechanical properties and the accumulation of stresses. Radiolytic oxidation is caused by the reaction of oxidizing species from the carbon dioxide coolant gas with the graphite, these species being produced by gamma radiation. Radiolytic oxidation reduces the density and hence the moderating capability of the graphite, but also reduces strength affecting the integrity of core components. In order to manage continued operation over the planned lifetimes of their power stations, BNFL needed to extend their database of the effects of these two phenomena on their graphite cores through an irradiation experiment. This paper will discuss the background, purpose, and the processes taken and planned (i.e. post irradiation examination) to ensure meaningful data on the graphite core material is obtained from the irradiation experiment.
Characterization Treatment And Conditioning Of Radioactive Graphite From Decommissioning Of Nuclear Reactors
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Author : International Atomic Energy Agency
language : en
Publisher: IAEA
Release Date : 2006
Characterization Treatment And Conditioning Of Radioactive Graphite From Decommissioning Of Nuclear Reactors written by International Atomic Energy Agency and has been published by IAEA this book supported file pdf, txt, epub, kindle and other format this book has been release on 2006 with Business & Economics categories.
Graphite has been used as a moderator and reflector of neutrons in more than 100nuclear power plants and in many research and plutonium-production reactors. It is usedprimarily as a neutron reflector or neutron moderator, although graphite is also used for other features of reactor cores, such as fuel sleeves. Many of the graphite-moderated reactors are now quite old, with some already shutdown. Therefore radioactive graphite dismantling and the management of radioactive graphite waste are becoming an increasingly important issue for a number of IAEA Member States. This report provides a comprehensive discussion of radioactive graphite waste characterization, handling, conditioning and disposal throughout the operating and decommissioning life cycle.