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Author : U.S. Atomic Energy Commission. Division of Reactor Development and Technology
Publisher : Unknown
Page : 56 pages
File Size : 44,6 Mb
Release : 1972
Category : Gas cooled reactors
ISBN : UOM:39015095074970
Author : Oak Ridge National Laboratory
Publisher : Unknown
Page : 260 pages
File Size : 52,7 Mb
Release : 1969
Category : Breeder reactors
ISBN : UOM:39015095068402
Author : Anonim
Publisher : Unknown
Page : 46 pages
File Size : 45,7 Mb
Release : 1972
Category : Electronic
ISBN : OCLC:251410773
Author : Oak Ridge National Laboratory,Babcock & Wilcox Company,Westinghouse Electric Corporation
Publisher : Unknown
Page : 241 pages
File Size : 44,7 Mb
Release : 1980
Category : Electronic
ISBN : OCLC:86055567
Author : Oak Ridge National Laboratory
Publisher : Unknown
Page : 236 pages
File Size : 53,8 Mb
Release : 1969
Category : Gas cooled reactors
ISBN : MINN:31951D03596235T
Author : Tetsuaki Takeda,Yoshiyuki Inagaki
Publisher : Academic Press
Page : 478 pages
File Size : 51,8 Mb
Release : 2021-02-24
Category : Business & Economics
ISBN : 9780128210321
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 : R. C. Holmes,L. Bernath,E. W. Hones
Publisher : Unknown
Page : 56 pages
File Size : 42,5 Mb
Release : 1958
Category : Heavy water reactors
ISBN : UOM:39015086425769
Author : John Graham
Publisher : Elsevier
Page : 390 pages
File Size : 40,5 Mb
Release : 2012-12-02
Category : Technology & Engineering
ISBN : 9780323152655
Fast Reactor Safety deals with safety design criteria and methodology for fast reactors. Topics covered include safety evaluation methods, system disturbances, containment, and licensing. The characteristics of fast reactors, including heat ratings and coolants, are also discussed. Comprised of six chapters, this book opens with an overview of methods used to evaluate nuclear safety, along with neutron kinetics, thermal and feedback effects, and fault tree analysis. The reader is then introduced to possible system disturbances in relation to three distinct fast reactor systems: liquid-metal-cooled fast breeder reactors, gas-cooled fast breeder reactors, and steam-cooled fast breeder reactors. The next chapter looks at safety criteria that are set to define the design of a safe plant, together with the safety features that might be included. The remaining chapters focus on the particular problems of a sodium-cooled design; containment building and primary circuit and vessel containment; and licensing of the plant. This monograph is intended for graduates and undergraduates in nuclear engineering who are attending courses in reactor safety.
Author : Baldev Raj,P. Chellapandi,P.R. Vasudeva Rao
Publisher : CRC Press
Page : 901 pages
File Size : 49,5 Mb
Release : 2015-04-15
Category : Science
ISBN : 9781466587694
Sodium Fast Reactors with Closed Fuel Cycle delivers a detailed discussion of an important technology that is being harnessed for commercial energy production in many parts of the world. Presenting the state of the art of sodium-cooled fast reactors with closed fuel cycles, this book:Offers in-depth coverage of reactor physics, materials, design, s
Author : G. Sofer
Publisher : Unknown
Page : 186 pages
File Size : 44,7 Mb
Release : 1961
Category : Breeder reactors
ISBN : MINN:31951D03913422T
Author : Willem Frederik Geert van Rooijen
Publisher : IOS Press
Page : 160 pages
File Size : 50,9 Mb
Release : 2006
Category : Technology & Engineering
ISBN : 1586036963
The Generation IV Forum is an international nuclear energy research initiative aimed at developing the fourth generation of nuclear reactors, envisaged to enter service halfway the 21st century. One of the Generation IV reactor systems is the Gas Cooled Fast Reactor (GCFR), the subject of study in this thesis. The Generation IV reactor concepts should improve all aspects of nuclear power generation. Within Generation IV, the GCFR concept specifically targets sustainability of nuclear power generation. The Gas Cooled Fast Reactor core power density is high in comparison to other gas cooled reactor concepts. Like all nuclear reactors, the GCFR produces decay heat after shut down, which has to be transported out of the reactor under all circumstances. The layout of the primary system therefore focuses on using natural convection Decay Heat Removal (DHR) where possible, with a large coolant fraction in the core to reduce friction losses.
Author : Anonim
Publisher : Unknown
Page : 478 pages
File Size : 45,9 Mb
Release : 1958
Category : Nuclear energy
ISBN : UOM:39015086531806
Author : Michael Tokar
Publisher : Unknown
Page : 136 pages
File Size : 50,8 Mb
Release : 1976
Category : Gas cooled reactors
ISBN : UOM:39015041107445
Author : Alan E. Waltar,Donald R. Todd,Pavel V. Tsvetkov
Publisher : Springer Science & Business Media
Page : 717 pages
File Size : 48,5 Mb
Release : 2011-09-28
Category : Technology & Engineering
ISBN : 9781441995728
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 : J. S. Brunhouse
Publisher : Unknown
Page : 70 pages
File Size : 51,5 Mb
Release : 1961
Category : Gas cooled reactors
ISBN : UOM:39015095163583