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Author: Athanasia Tzelepi
Publisher:
ISBN: 9780803177260
Category : Graphite
Languages : en
Pages : 0
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Book Description
"This compilation of Selected Technical Papers, STP1639, Graphite Testing for Nuclear Applications : The Validity and Extension of Test Methods for Material Exposed to Operating Reactor Environments, contains peer-reviewed papers that were presented at a symposium held virtually September 23-24, 2021. The symposium was sponsored by ASTM International Committee D02 on Petroleum Products, Liquid Fuels, and Lubricants, and Subcommittee D02.F0 Manufactured Carbon and Graphite Products"--
Author: Athanasia Tzelepi
Publisher:
ISBN: 9780803177260
Category : Graphite
Languages : en
Pages : 0
Get Book Here
Book Description
"This compilation of Selected Technical Papers, STP1639, Graphite Testing for Nuclear Applications : The Validity and Extension of Test Methods for Material Exposed to Operating Reactor Environments, contains peer-reviewed papers that were presented at a symposium held virtually September 23-24, 2021. The symposium was sponsored by ASTM International Committee D02 on Petroleum Products, Liquid Fuels, and Lubricants, and Subcommittee D02.F0 Manufactured Carbon and Graphite Products"--
Author: William B. Cottrell
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 178
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Book Description
Author: Tetsuaki Takeda
Publisher: Academic Press
ISBN: 012821032X
Category : Technology & Engineering
Languages : en
Pages : 500
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Book Description
High-Temperature Gas Reactors is the fifth volume in the JSME Series on Thermal and Nuclear Power Generation. Series Editor Yasuo Koizumi and his Volume editors Tetsuaki Takeda and Yoshiyuki Inagaki present the latest research on High-Temperature Gas Reactor (HTGR) development and utilization, beginning with an analysis of the history of HTGRs. A detailed analysis of HTGR design features, including reactor core design, cooling tower design, pressure vessel design, I&C factors and safety design, provides readers with a solid understanding of how to develop efficient and safe HTGR within a nuclear power plant.The authors combine their knowledge to present a guide on the safety of HTGRs throughout the entire reactor system, drawing on their unique experience to pass on lessons learned and best practices to support professionals and researchers in their design and operation of these advanced reactor types. Case studies of critical testing carried out by the authors provide the reader with firsthand information on how to conduct tests safely and effectively and an understanding of which responses are required in unexpected incidents to achieve their research objectives. An analysis of technologies and systems in development and testing stages offer the reader a look to the future of HTGRs and help to direct and inform their further research in heat transfer, fluid-dynamics, fuel options and advanced reactor facility selection.This volume is of interest for nuclear and thermal energy engineers and researchers focusing on HTGRs, HTGR plant designers and operators, regulators, post graduate students of nuclear engineering, national labs, government officials and agencies in power and energy policy and regulations. - Written by the leaders and pioneers in nuclear research at the Japanese Society of Mechanical Engineers and draws upon their combined wealth of knowledge and experience - Includes real examples and case studies from Japan, the US and Europe to provide a deeper learning opportunity with practical benefits - Considers the societal impact and sustainability concerns and goals throughout the discussion - Includes safety factors and considerations, as well as unique results from performance testing of HTGR systems
Author:
Publisher:
ISBN:
Category : Energy development
Languages : en
Pages : 720
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Book Description
Author:
Publisher:
ISBN:
Category : Weights and measures
Languages : en
Pages : 318
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Book Description
Author: T.D. Burchell
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 568
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Book Description
This study begins with a review of carbon materials, emphasizing structure and chemical bonding in various forms of carbon. It then goes on to discuss advanced technologies for the manufacture and modification of carbon-based materials and their practical applications.
Author: Salvatore J. Rand
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 264
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Book Description
Author: R. E. Nightingale
Publisher: Academic Press
ISBN: 1483258483
Category : Technology & Engineering
Languages : en
Pages : 566
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Book Description
Nuclear Graphite focuses on the development and uses of nuclear graphite, including machining practices, manufacture, nuclear properties and structure, radiation, and electrical resistance. The selection first discusses the applications of graphite in the nuclear industry, machining practices, and manufacture. Discussions focus on early, current, and future applications of graphite, impregnation, graphitization, purification, general machining techniques, and equipment and methods in the nuclear industry. The book then examines the structure and nuclear and properties of graphite. The text evaluates radiation-induced structural and dimensional changes; radiation effects on electrical and thermal properties; and radiation effects on mechanical properties. Topics include radiation effects on crystal structure, electrical resistance, thermoelectric power, magnetoresistance, coefficient of friction, irradiation under stress, and elastic moduli of nuclear graphite. The book also ponders on stored energy, annealing radiation effects, and gas-graphite systems. The selection is a dependable source of data for readers interested in the applications of nuclear graphite.
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1146
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Book Description
Author: International Atomic Energy Agency
Publisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 88
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Book Description
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.
