Thermal and Flow Design of Helium-cooled Reactors

Thermal and Flow Design of Helium-cooled Reactors

Author: Gilbert Melese

Publisher:

Published: 1984

Total Pages: 444

ISBN-13:

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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.


Book Synopsis Thermal and Flow Design of Helium-cooled Reactors by : Gilbert Melese

Download or read book Thermal and Flow Design of Helium-cooled Reactors written by Gilbert Melese and published by . This book was released on 1984 with total page 444 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.


Thermal Design of Nuclear Reactors

Thermal Design of Nuclear Reactors

Author: R. H. S. Winterton

Publisher: Elsevier

Published: 2014-04-23

Total Pages: 206

ISBN-13: 1483145247

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Thermal Design of Nuclear Reactors


Book Synopsis Thermal Design of Nuclear Reactors by : R. H. S. Winterton

Download or read book Thermal Design of Nuclear Reactors written by R. H. S. Winterton and published by Elsevier. This book was released on 2014-04-23 with total page 206 pages. Available in PDF, EPUB and Kindle. Book excerpt: Thermal Design of Nuclear Reactors


High Temperature Gas-cooled Reactors

High Temperature Gas-cooled Reactors

Author: Tetsuaki Takeda

Publisher: Academic Press

Published: 2021-02-24

Total Pages: 478

ISBN-13: 012821032X

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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.


Book Synopsis High Temperature Gas-cooled Reactors by : Tetsuaki Takeda

Download or read book High Temperature Gas-cooled Reactors written by Tetsuaki Takeda and published by Academic Press. This book was released on 2021-02-24 with total page 478 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.


Heat Transfer and Fluid Flow in Nuclear Systems

Heat Transfer and Fluid Flow in Nuclear Systems

Author: Henri Fenech

Publisher: Elsevier

Published: 2013-10-22

Total Pages: 591

ISBN-13: 148315078X

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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.


Book Synopsis Heat Transfer and Fluid Flow in Nuclear Systems by : Henri Fenech

Download or read book Heat Transfer and Fluid Flow in Nuclear Systems written by Henri Fenech and published by Elsevier. This book was released on 2013-10-22 with total page 591 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.


An Evaluation of High-temperature Gas-cooled Reactors

An Evaluation of High-temperature Gas-cooled Reactors

Author: Oak Ridge National Laboratory

Publisher:

Published: 1969

Total Pages: 236

ISBN-13:

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Book Synopsis An Evaluation of High-temperature Gas-cooled Reactors by : Oak Ridge National Laboratory

Download or read book An Evaluation of High-temperature Gas-cooled Reactors written by Oak Ridge National Laboratory and published by . This book was released on 1969 with total page 236 pages. Available in PDF, EPUB and Kindle. Book excerpt:


A Parametric Study of the Gas-cooled Reactor Concept

A Parametric Study of the Gas-cooled Reactor Concept

Author: Hanford Atomic Products Operation

Publisher:

Published: 1958

Total Pages: 44

ISBN-13:

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Book Synopsis A Parametric Study of the Gas-cooled Reactor Concept by : Hanford Atomic Products Operation

Download or read book A Parametric Study of the Gas-cooled Reactor Concept written by Hanford Atomic Products Operation and published by . This book was released on 1958 with total page 44 pages. Available in PDF, EPUB and Kindle. Book excerpt:


Status of and Prospects for Gas-cooled Reactors

Status of and Prospects for Gas-cooled Reactors

Author: International Atomic Energy Agency

Publisher:

Published: 1984

Total Pages: 294

ISBN-13:

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Book Synopsis Status of and Prospects for Gas-cooled Reactors by : International Atomic Energy Agency

Download or read book Status of and Prospects for Gas-cooled Reactors written by International Atomic Energy Agency and published by . This book was released on 1984 with total page 294 pages. Available in PDF, EPUB and Kindle. Book excerpt:


Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor

Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor

Author: Willem Frederik Geert van Rooijen

Publisher: IOS Press

Published: 2006

Total Pages: 160

ISBN-13: 9781586036966

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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.


Book Synopsis Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor by : Willem Frederik Geert van Rooijen

Download or read book Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor written by Willem Frederik Geert van Rooijen and published by IOS Press. This book was released on 2006 with total page 160 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.


Design Analysis of a Subsonic Nuclear-powered Logistic Airplane with Helium-cooled Reactor

Design Analysis of a Subsonic Nuclear-powered Logistic Airplane with Helium-cooled Reactor

Author:

Publisher:

Published: 1959

Total Pages: 258

ISBN-13:

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Book Synopsis Design Analysis of a Subsonic Nuclear-powered Logistic Airplane with Helium-cooled Reactor by :

Download or read book Design Analysis of a Subsonic Nuclear-powered Logistic Airplane with Helium-cooled Reactor written by and published by . This book was released on 1959 with total page 258 pages. Available in PDF, EPUB and Kindle. Book excerpt:


In-pile Heat Transfer Studies of Roughened Helium-cooled Reactor Fuel Elements

In-pile Heat Transfer Studies of Roughened Helium-cooled Reactor Fuel Elements

Author:

Publisher:

Published: 1967

Total Pages: 9

ISBN-13:

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Book Synopsis In-pile Heat Transfer Studies of Roughened Helium-cooled Reactor Fuel Elements by :

Download or read book In-pile Heat Transfer Studies of Roughened Helium-cooled Reactor Fuel Elements written by and published by . This book was released on 1967 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: