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Book Modelling and Measuring Reactor Core Graphite Properties and Performance

Download or read book Modelling and Measuring Reactor Core Graphite Properties and Performance written by Gareth B. Neighbour and published by Royal Society of Chemistry. This book was released on 2012 with total page 227 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Book Physical Methods for Materials Characterisation

Download or read book Physical Methods for Materials Characterisation written by Peter E. J. Flewitt and published by CRC Press. This book was released on 2017-12-06 with total page 725 pages. Available in PDF, EPUB and Kindle. Book excerpt: This completely revised and expanded new edition covers the full range of techniques now available for the investigation of materials structure and accurate quantitative determination of microstructural features within materials. It continues to provide the best introductory resource for understanding the interrelationship between microstructure and physical, mechanical, and chemical properties, as well as selection and application of techniques for both basic and applied studies. In particular, changes have been made to reflect developments in analysis of nanoscale and biological materials.

Book Scientific and Technical Aerospace Reports

Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1984 with total page 1278 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Nuclear Science Abstracts

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1974-07 with total page 978 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Understanding and Mitigating Ageing in Nuclear Power Plants

Download or read book Understanding and Mitigating Ageing in Nuclear Power Plants written by Philip G Tipping and published by Elsevier. This book was released on 2010-10-26 with total page 953 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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

Book Processing of Irradiated Graphite to Meet Acceptance Criteria for Waste Disposal

Download or read book Processing of Irradiated Graphite to Meet Acceptance Criteria for Waste Disposal written by International Atomic Energy Agency and published by IAEA Tecdoc Series No. 1790. This book was released on 2016 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Graphite is widely used in the nuclear industry and in research facilities and this has led to increasing amounts of irradiated graphite residing in temporary storage facilities pending disposal. This publication arises from a coordinated research project (CRP) on the processing of irradiated graphite to meet acceptance criteria for waste disposal.

Book Industrial Carbon and Graphite Materials

Download or read book Industrial Carbon and Graphite Materials written by Hubert Jaeger and published by John Wiley & Sons. This book was released on 2021-03-05 with total page 1008 pages. Available in PDF, EPUB and Kindle. Book excerpt: An excellent overview of industrial carbon and graphite materials, especially their manufacture, use and applications in industry. Following a short introduction, the main part of this reference deals with industrial forms, their raw materials, properties and manifold applications. Featuring chapters on carbon and graphite materials in energy application, and as catalysts. It covers all important classes of carbon and graphite, from polygranular materials to fullerenes, and from activated carbon to carbon blacks and nanoforms of carbon. Indispensable for chemists and engineers working in such fields as steel, aluminum, electrochemistry, nanotechnology, catalyst, carbon fibres and lightweight composites.

Book Nuclear Science Abstracts

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1974-03 with total page 1100 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Ignalina RBMK 1500   a source book

Download or read book Ignalina RBMK 1500 a source book written by Kazys Almenas and published by . This book was released on 1998 with total page 198 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Energy Research Abstracts

Download or read book Energy Research Abstracts written by and published by . This book was released on 1985 with total page 712 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Basic Studies in the Field of High temperature Engineering

Download or read book Basic Studies in the Field of High temperature Engineering written by Nihon Genshiryoku Kenkyūjo and published by Paris, France : Nuclear Energy Agency, Organisation for Economic Co-operation and Development. This book was released on 2002 with total page 370 pages. Available in PDF, EPUB and Kindle. Book excerpt: In response to increasing interest in high-temperature, gas-cooled reactors (HTGRs) in many countries and the need for improved materials for nuclear applications in high-temperature environments, the NEA organised a Second Information Exchange Meeting on Basic Studies in the Field of High-temperature Engineering. These proceedings provide an overview of the activities being carried out in eight countries, the improvement of material properties for HTGR application, in-core monitoring methods and properties of irradiated graphite, and HTGR fuel fabrication and performance.

Book Monthly Catalogue  United States Public Documents

Download or read book Monthly Catalogue United States Public Documents written by and published by . This book was released on 1983 with total page 1050 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Monthly Catalog of United States Government Publications

Download or read book Monthly Catalog of United States Government Publications written by United States. Superintendent of Documents and published by . This book was released on 1983 with total page 1588 pages. Available in PDF, EPUB and Kindle. Book excerpt: February issue includes Appendix entitled Directory of United States Government periodicals and subscription publications; September issue includes List of depository libraries; June and December issues include semiannual index

Book Characterization  Treatment and Conditioning of Radioactive Graphite from Decommissioning of Nuclear Reactors

Download or read book Characterization Treatment and Conditioning of Radioactive Graphite from Decommissioning of Nuclear Reactors written by International Atomic Energy Agency and published by IAEA. This book was released on 2006 with total page 88 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Book Handbook of Carbon  Graphite  Diamonds and Fullerenes

Download or read book Handbook of Carbon Graphite Diamonds and Fullerenes written by Hugh O. Pierson and published by William Andrew. This book was released on 2012-12-02 with total page 420 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book is a review of the science and technology of the element carbon and its allotropes: graphite, diamond and the fullerenes. This field has expanded greatly in the last three decades stimulated by many major discoveries such as carbon fibers, low-pressure diamond, and the fullerenes. The need for such a book has been felt for some time. These carbon materials are very different in structure and properties. Some are very old (charcoal), others brand new (the fullerenes). They have different applications and markets and are produced by different segments of the industry.Few studies are available that attempt to review the entire field of carbon as a whole discipline. Moreover these studies were written several decades ago and a generally outdated since the development of the technology is moving very rapidly and scope of applications is constantly expanding and reaching into new fields such as aerospace, automotive, semiconductors, optics, and electronics. In this book the author provides a valuable, up-to-date account of both the newer and traditional forms of carbon, both naturally occurring and man-made. This volume will be a valuable resource for both specialists in, and occasional users of carbon materials.

Book Advances in High Temperature Gas Cooled Reactor Fuel Technology

Download or read book Advances in High Temperature Gas Cooled Reactor Fuel Technology written by International Atomic Energy Agency and published by . This book was released on 2012-06 with total page 639 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments. These comprise two specific benchmark exercises with the application of HTGR fuel performance and fission product release codes, which helped compare the quality and validity of the computer models against experimental data. The project participants also examined techniques for fuel characterization and advanced quality assessment/quality control. The key exercise included a round-robin experimental study on the measurements of fuel kernel and particle coating properties of recent Korean, South African and US coated particle productions applying the respective qualification measures of each participating Member State. The summary report documents the results and conclusions achieved by the project and underlines the added value to contemporary knowledge on HTGR fuel.

Book Physics of Nuclear Reactors

Download or read book Physics of Nuclear Reactors written by P. Mohanakrishnan and published by Elsevier. This book was released on 2021-05-19 with total page 786 pages. Available in PDF, EPUB and Kindle. Book excerpt: Physics of Nuclear Reactors presents a comprehensive analysis of nuclear reactor physics. Editors P. Mohanakrishnan, Om Pal Singh, and Kannan Umasankari and a team of expert contributors combine their knowledge to guide the reader through a toolkit of methods for solving transport equations, understanding the physics of reactor design principles, and developing reactor safety strategies. The inclusion of experimental and operational reactor physics makes this a unique reference for those working and researching nuclear power and the fuel cycle in existing power generation sites and experimental facilities. The book also includes radiation physics, shielding techniques and an analysis of shield design, neutron monitoring and core operations. Those involved in the development and operation of nuclear reactors and the fuel cycle will gain a thorough understanding of all elements of nuclear reactor physics, thus enabling them to apply the analysis and solution methods provided to their own work and research. This book looks to future reactors in development and analyzes their status and challenges before providing possible worked-through solutions. Cover image: Kaiga Atomic Power Station Units 1 - 4, Karnataka, India. In 2018, Unit 1 of the Kaiga Station surpassed the world record of continuous operation, at 962 days. Image courtesy of DAE, India. Includes methods for solving neutron transport problems, nuclear cross-section data and solutions of transport theory Dedicates a chapter to reactor safety that covers mitigation, probabilistic safety assessment and uncertainty analysis Covers experimental and operational physics with details on noise analysis and failed fuel detection