Thermal and Flow Design of Helium-cooled Reactors PDF Download
Are you looking for read ebook online? Search for your book and save it on your Kindle device, PC, phones or tablets. Download Thermal and Flow Design of Helium-cooled Reactors PDF full book. Access full book title Thermal and Flow Design of Helium-cooled Reactors by Gilbert Melese. Download full books in PDF and EPUB format.
Author: Gilbert Melese
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 444
Get Book Here
Book Description
This source book provides both an overview of gas-cooled reactors and a detailed look at the high-temperature gas-cooled reactor (HTGR). Taking a worldwide perspective, this book reviews the early development of the HTGR and explores potential future development and applications.
Author: Gilbert Melese
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 444
Get Book Here
Book Description
This source book provides both an overview of gas-cooled reactors and a detailed look at the high-temperature gas-cooled reactor (HTGR). Taking a worldwide perspective, this book reviews the early development of the HTGR and explores potential future development and applications.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Get Book Here
Book Description
This book continues the American Nuclear Society's series of monographs on nuclear science and technology. Chapters of the book include information on the first-generation gas-cooled reactors; HTGR reactor developments; reactor core heat transfer; mechanical problems related to the primary coolant circuit; HTGR design bases; core thermal design; gas turbines; process heat HTGR reactors; GCFR reactor thermal hydraulics; and gas cooling of fusion reactors.
Author: R. H. S. Winterton
Publisher: Elsevier
ISBN: 1483145247
Category : Technology & Engineering
Languages : en
Pages : 206
Get Book Here
Book Description
Thermal Design of Nuclear Reactors
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 26
Get Book Here
Book Description
Author: Willem Frederik Geert van Rooijen
Publisher: IOS Press
ISBN: 9781586036966
Category : Technology & Engineering
Languages : en
Pages : 160
Get Book Here
Book Description
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: Tetsuaki Takeda
Publisher: Academic Press
ISBN: 012821032X
Category : Business & Economics
Languages : en
Pages : 478
Get Book Here
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: Henri Fenech
Publisher: Elsevier
ISBN: 148315078X
Category : Science
Languages : en
Pages : 591
Get Book Here
Book Description
Heat Transfer and Fluid in Flow Nuclear Systems discusses topics that bridge the gap between the fundamental principles and the designed practices. The book is comprised of six chapters that cover analysis of the predicting thermal-hydraulics performance of large nuclear reactors and associated heat-exchangers or steam generators of various nuclear systems. Chapter 1 tackles the general considerations on thermal design and performance requirements of nuclear reactor cores. The second chapter deals with pressurized subcooled light water systems, and the third chapter covers boiling water reactor systems. Chapter 4 tackles liquid metal cooled systems, while Chapter 5 discusses helium cooled systems. The last chapter deals with heat-exchangers and steam generators. The book will be of great help to engineers, scientists, and graduate students concerned with thermal and hydraulic problems.
Author: R. H. Armstrong
Publisher:
ISBN:
Category : Chemical reactions
Languages : en
Pages : 60
Get Book Here
Book Description
A study was made of approximately 132 reports on gas-cooled reactors and related subjects. Charts and tables containing the following information are included: all available reactor information, reactor flow diagrams of suggested concepts, possible core arrangement at core cross section, typical fuel and moderator cell, possible fuel types for unit fuel cell, the properties of materials for moderators and reflectors. the compatibility of gases and base fuel materials at maximum surface temperatures, maximum interface temperatures of fuel elements and core-jacket combinations, allowable operating temperatures and compatibility of gases and various metals. preferences for gas coolants, cost and availability of gases plant thermal cycle efficiencies, thermal properties of gases, pumping power and reactor coolant inlet temperatures, obtainable heat fluxes, composition and physical properties of potential cladding materials. atomic and thermal properties of cladding materials, fabrication characteristics and costs of cladding materials, possible process applications of gases at high temperature, and potential high-temperature materials. The various categories of gas-cooled reactors and examples of each type are discussed. A gas reactor program for high-temperature experimentation is proposed.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 9
Get Book Here
Book Description
Author: General Dynamics Corporation. General Atomic Division. John Jay Hopkins Laboratory for Pure and Applied Science
Publisher:
ISBN:
Category : Gas cooled reactors
Languages : en
Pages : 246
Get Book Here
Book Description
