Fast Reactor Database 2006 Update PDF Download
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Author: International Atomic Energy Agency
Publisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 462
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Book Description
Liquid metal cooled fast reactors (LMFRs) have been under development for about 50 years. The fast reactor database (FRDB) summarised in this report contains detailed design and operational data on 37 fast reactor plants, their thermal power ranging from 10 to 4000 MW, covering experimental, prototype, demonstration and commercial size LMFRs. Data includes physical, hydraulic and thermomechanical characteristics, technological requirements and methods and criteria to ensure safe operation, as well as dimensions, materials information and main design features and performance parameters of reactor cores, components and various systems, along with sketches and drawings.
Author: International Atomic Energy Agency
Publisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 462
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Book Description
Liquid metal cooled fast reactors (LMFRs) have been under development for about 50 years. The fast reactor database (FRDB) summarised in this report contains detailed design and operational data on 37 fast reactor plants, their thermal power ranging from 10 to 4000 MW, covering experimental, prototype, demonstration and commercial size LMFRs. Data includes physical, hydraulic and thermomechanical characteristics, technological requirements and methods and criteria to ensure safe operation, as well as dimensions, materials information and main design features and performance parameters of reactor cores, components and various systems, along with sketches and drawings.
Author: International Atomic Energy Agency
Publisher:
ISBN: 9781523130191
Category : Fast reactors
Languages : en
Pages : 0
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Book Description
"Based on a recommendation from the Technical Working Group on Fast Reactors, this publication is a regular update of previous publications on fast reactor technology. The publication provides comprehensive and detailed information on the technology of fast neutron reactors. The focus is on practical issues that are useful to engineers, scientists, managers, university students and professors. The main issues of discussion are experience in design, construction, operation and decommissioning, various areas of research and development, engineering, safety and national strategies, and public acceptance of fast reactors. In the summary the reader will find national strategies, international initiatives on innovative (i.e. Generation IV) systems and an assessment of public acceptance as related to fast reactors."--Résumé de l'éditeur.
Author: Alan E. Waltar
Publisher: Springer Science & Business Media
ISBN: 1441995722
Category : Technology & Engineering
Languages : en
Pages : 717
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Book Description
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: Naoto Kasahara
Publisher: Springer
ISBN: 9811028214
Category : Technology & Engineering
Languages : en
Pages : 307
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Book Description
This book describes the fast reactor (FR), a type of new reactor for nuclear plants, currently under research and development. The book targets young researchers and engineers who will be charged with commercializing this new type of reactor to lead to the development of new components and systems for improved plant reliability and economy. This volume also helps readers to understand the methods of integrating the power plant in its entirety, from the reactor core to all of the various systems and components, and teaches the way of thinking that forms the background of these methods. This background includes the various organizational and management issues that are encountered as projects move forward and will be explored in great detail based on actual design and construction experience with Japan’s prototype FR, Monju.
Author: Masaki Morishita
Publisher: Academic Press
ISBN: 0128240776
Category : Technology & Engineering
Languages : en
Pages : 666
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Book Description
Sodium-cooled Fast Reactors is the third volume in the JSME Series on Thermal and Nuclear Power Generation, which presents a comprehensive view of the latest research and activities from around the globe. Volume Editors Masaki Morishita and Hiroyuki Ohshima, along with their team of expert contributors, combine their knowledge and experience to provide a solid understanding of the history of SFRs and work carried out in Japan to date. This book uniquely includes case studies from these global regions to highlight SFR uses, benefits and challenges, focusing on their safety, design, operation, and maintenance. Unique to this publication, the JSME cover key technological advances which will shape power generation of the future, including developments in the use of AI for design. Drawing on their unique experience, the authors pass on lessons learned and best practices to support professionals and researchers in their development and design of this advanced reactor type. - 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 mainly from Japan 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 SFR systems
Author: Thomas Schulenberg
Publisher: Springer Nature
ISBN: 3662649195
Category : Science
Languages : en
Pages : 190
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Book Description
This book is intended for readers who want to learn more about fourth-generation nuclear reactors without having to delve deeply into nuclear technology. These nuclear reactors are a number of visionary concepts for which special criteria have been set by the Generation IV International Forum with regard to safety, sustainability and economic efficiency. The book therefore describes, among other things, innovative water- and liquid-metal-cooled reactors, high-temperature and molten-salt reactors, and discusses their significance for the economy and society. The author imparts relevant basic knowledge of nuclear technology and then uses some illustrative examples to show what future opportunities this fourth generation of nuclear reactors will offer, but also what challenges will be associated with it. About the author Prof. Dr. -Ing. Thomas Schulenberg studied physics and mechanical engineering and received his doctorate in the field of sodium-cooled reactors. During his fourteen-year industrial career, he developed gas turbines for conventional power plants. Since 2000, Prof. Schulenberg was the head of the Institute for Nuclear and Energy Technology at the Karlsruhe Institute of Technology, where he lectured on conventional power plant technology as well as nuclear power plant technology. As a member of the steering committee for fourth-generation water-cooled reactors, he was actively involved in the Generation IV International Forum for many years.
Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201364104
Category : Science
Languages : en
Pages : 0
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Book Description
As a part of the IAEA efforts for knowledge preservation and data retrieval, this publication compiles and documents significant aspects of fast reactor engineering development and experience. Its focus is on research and development activities, experience with experimental facilities, and criteria for comparison liquid metal coolants.
Author: Neil E. Todreas
Publisher: CRC Press
ISBN: 1351030485
Category : Science
Languages : en
Pages : 1003
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Book Description
Nuclear Systems, Volume I: Thermal Hydraulic Fundamentals, Third Edition, provides an in-depth introduction to nuclear power, focusing on thermal hydraulic design and analysis of the nuclear core and other key nuclear plant components. The authors stress the integration of fluid flow and heat transfer as applied to all power reactor types and energy source distribution. They cover nuclear reactor concepts and systems, including GEN III+, GEN IV, and SMR reactors and new power cycles. The text includes new chapter examples and problems using concept parameters, full-color text and art, computer programs, figure slides, and a solutions manual. FEATURES Rigorous coverage of nuclear power generation fundamentals Description and analysis of the latest nuclear power plant designs and technologies Extensive examples in each chapter to illustrate the analysis methods which have been presented New full-color art and text features to enhance the presentation of topics Integration of fluid flow and heat transfer as applied to single- and two-phase coolants Readers will develop the knowledge and design skills needed to improve the next generation of nuclear reactors.
Author: IAEA
Publisher: International Atomic Energy Agency
ISBN: 9201024215
Category : Technology & Engineering
Languages : en
Pages : 67
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Book Description
This publication aims to outline credible technical options for managing separated plutonium. There is no attempt to rank or rate any of the options, instead the intent is to inform the reader of the technical merits of the various options and the state of their development. It is primarily focused on Member States that have adopted a closed fuel cycle policy but can also be of value to other Member States, specifically their decision makers and other stakeholders involved in potential future nuclear fuel cycles, by informing them on life cycle options and energy policy.
Author: Neil E. Todreas
Publisher: CRC Press
ISBN: 0415802873
Category : Science
Languages : en
Pages : 1037
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Book Description
Nuclear power is in the midst of a generational change—with new reactor designs, plant subsystems, fuel concepts, and other information that must be explained and explored—and after the 2011 Japan disaster, nuclear reactor technologies are, of course, front and center in the public eye. Written by leading experts from MIT, Nuclear Systems Volume I: Thermal Hydraulic Fundamentals, Second Edition provides an in-depth introduction to nuclear power, with a focus on thermal hydraulic design and analysis of the nuclear core. A close examination of new developments in nuclear systems, this book will help readers—particularly students—to develop the knowledge and design skills required to improve the next generation of nuclear reactors. Includes a CD-ROM with Extensive Tables for Computation Intended for experts and senior undergraduate/early-stage graduate students, the material addresses: Different types of reactors Core and plant performance measures Fission energy generation and deposition Conservation equations Thermodynamics Fluid flow Heat transfer Imparting a wealth of knowledge, including their longtime experience with the safety aspects of nuclear installations, authors Todreas and Kazimi stress the integration of fluid flow and heat transfer, various reactor types, and energy source distribution. They cover recent nuclear reactor concepts and systems, including Generation III+ and IV reactors, as well as new power cycles. The book features new chapter problems and examples using concept parameters, and a solutions manual is available with qualifying course adoption.
