Proceedings of the 12th International Conference on Nuclear Engineering (ICONE12)--2004: Safety and security. Fuel cycle and high level waste management. Thermal hydraulics PDF Download

Author:
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 902

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Author: International Conference on Nuclear Engineering
Publisher:
ISBN:
Category :
Languages : en
Pages : 907

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Author:
Publisher:
ISBN: 9780791846896
Category : Nuclear engineering
Languages : en
Pages : 877

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"Nuclear energy--powering the future"--Cover.

Author:
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 1034

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Author: Dan Gabriel Cacuci
Publisher: Springer Science & Business Media
ISBN: 0387981306
Category : Science
Languages : en
Pages : 3701

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This is an authoritative compilation of information regarding methods and data used in all phases of nuclear engineering. Addressing nuclear engineers and scientists at all levels, this book provides a condensed reference on nuclear engineering since 1958.

Author: Tetsuaki Takeda
Publisher: Academic Press
ISBN: 012821032X
Category : Technology & Engineering
Languages : en
Pages : 500

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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: S. C. Singhal
Publisher: The Electrochemical Society
ISBN: 156677862X
Category : Science
Languages : en
Pages : 3058

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This issue of ECS Transactions contains papers from the Twelfth International Symposium on Solid Oxide Fuel Cells (SOFC-XII),a continuing biennial series of symposia. The papers deal with materials for cell components and fabrication methods for components and complete cells. Also contained are papers on cell electrochemical performance and its modelling, stacks and systems, and prototype testing of SOFC demonstration units for different applications.

Author: Alan E. Waltar
Publisher: Springer Science & Business Media
ISBN: 1441995722
Category : Technology & Engineering
Languages : en
Pages : 717

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This book is a complete update of the classic 1981 FAST BREEDER REACTORS textbook authored by Alan E. Waltar and Albert B. Reynolds, which , along with the Russian translation, served as a major reference book for fast reactors systems. Major updates include transmutation physics (a key technology to substantially ameliorate issues associated with the storage of high-level nuclear waste ), advances in fuels and materials technology (including metal fuels and cladding materials capable of high-temperature and high burnup), and new approaches to reactor safety (including passive safety technology), New chapters on gas-cooled and lead-cooled fast spectrum reactors are also included. Key international experts contributing to the text include Chaim Braun, (Stanford University) Ronald Omberg, (Pacific Northwest National Laboratory, Massimo Salvatores (CEA, France), Baldev Raj, (Indira Gandhi Center for Atomic Research, India) , John Sackett (Argonne National Laboratory), Kevan Weaver, (TerraPower Corporation) ,James Seinicki(Argonne National Laboratory). Russell Stachowski (General Electric), Toshikazu Takeda (University of Fukui, Japan), and Yoshitaka Chikazawa (Japan Atomic Energy Agency).

Author: Wim Voorbraak
Publisher: World Scientific
ISBN: 9814468290
Category : Science
Languages : en
Pages : 761

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This book gives the state of the art in the field of reactor dosimetry as applied in nuclear power plants and research reactors. Surveillance programs are presented for nuclear power plants in Europe, including Russia and Ukraine, USA, Argentina and Korea. New cross-section measurements from most of the European, American and Japanese research reactors are reported. The latest developments in computer code development for radiation transport and shielding calculations, and radiation measurement techniques are also highlighted.

Author: Nikolay Ivanov Kolev
Publisher: Springer Science & Business Media
ISBN: 3540929185
Category : Technology & Engineering
Languages : en
Pages : 761

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The nuclear thermal hydraulic is the science providing knowledge about the physical processes occurring during the transferring the fission heat released in structural materials due to nuclear reactions into its environment. Along its way to the environment the thermal energy is organized to provide useful mechanical work or useful heat or both. Chapter 1 contains introductory information about the heat release in the re- tor core, the thermal power and thermal power density in the fuel, structures and moderator, the influence of the thermal power density on the coolant temperature, the spatial distribution of the thermal power density. Finally some measures are introduced for equalizing of the spatial distribution of the thermal power density. Chapter 2 gives the methods for describing of the steady and of the transient temperature fields in the fuel elements. Some information is provided regarding influence of the cladding oxidation, hydrogen diffusion and of the corrosion pr- uct deposition on the temperature fields. Didactically the nuclear thermal hydraulic needs introductions at different level of complexity by introducing step by step the new features after the previous are clearly presented. The followed two Chapters serve this purpose. Chapter 3 describes mathematically the “simple” steady boiling flow in a pipe. The steady mass-, momentum- and energy conservation equations are solved at different level of complexity by removing one after the other simplifying assu- tions. First the idea of mechanical and thermodynamic equilibrium is introduced.