Author:
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 570
Book Description
Review of Power and Heat Reactor Designs
Author:
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 570
Book Description
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 570
Book Description
Why Nuclear Power Has Been a Flop
Author: Jack Devanney
Publisher: Bookbaby
ISBN: 9781098308964
Category :
Languages : en
Pages : 206
Book Description
This book is a collection of essays focused on the Gordian knot of our time, the closely coupled problems of energy poverty for billions of humans, and global warming for all humans. The central thesis of the book in that nuclear power is not only the only solution, it is a highly desirable solution, cheaper, safer, less intrusive on nature than all the alternatives.
Publisher: Bookbaby
ISBN: 9781098308964
Category :
Languages : en
Pages : 206
Book Description
This book is a collection of essays focused on the Gordian knot of our time, the closely coupled problems of energy poverty for billions of humans, and global warming for all humans. The central thesis of the book in that nuclear power is not only the only solution, it is a highly desirable solution, cheaper, safer, less intrusive on nature than all the alternatives.
High Temperature Gas-cooled Reactors
Author: Tetsuaki Takeda
Publisher: Academic Press
ISBN: 012821032X
Category : Technology & Engineering
Languages : en
Pages : 500
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
Publisher: Academic Press
ISBN: 012821032X
Category : Technology & Engineering
Languages : en
Pages : 500
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
Handbook of Generation IV Nuclear Reactors
Author: Igor Pioro
Publisher: Woodhead Publishing
ISBN: 0128226536
Category : Technology & Engineering
Languages : en
Pages : 1112
Book Description
Handbook of Generation IV Nuclear Reactors, Second Edition is a fully revised and updated comprehensive resource on the latest research and advances in generation IV nuclear reactor concepts. Editor Igor Pioro and his team of expert contributors have updated every chapter to reflect advances in the field since the first edition published in 2016. The book teaches the reader about available technologies, future prospects and the feasibility of each concept presented, equipping them users with a strong skillset which they can apply to their own work and research. - Provides a fully updated, revised and comprehensive handbook dedicated entirely to generation IV nuclear reactors - Includes new trends and developments since the first publication, as well as brand new case studies and appendices - Covers the latest research, developments and design information surrounding generation IV nuclear reactors
Publisher: Woodhead Publishing
ISBN: 0128226536
Category : Technology & Engineering
Languages : en
Pages : 1112
Book Description
Handbook of Generation IV Nuclear Reactors, Second Edition is a fully revised and updated comprehensive resource on the latest research and advances in generation IV nuclear reactor concepts. Editor Igor Pioro and his team of expert contributors have updated every chapter to reflect advances in the field since the first edition published in 2016. The book teaches the reader about available technologies, future prospects and the feasibility of each concept presented, equipping them users with a strong skillset which they can apply to their own work and research. - Provides a fully updated, revised and comprehensive handbook dedicated entirely to generation IV nuclear reactors - Includes new trends and developments since the first publication, as well as brand new case studies and appendices - Covers the latest research, developments and design information surrounding generation IV nuclear reactors
Thermal-Hydraulics of Water Cooled Nuclear Reactors
Author: Francesco D'Auria
Publisher: Woodhead Publishing
ISBN: 0081006799
Category : Technology & Engineering
Languages : en
Pages : 1200
Book Description
Thermal Hydraulics of Water-Cooled Nuclear Reactors reviews flow and heat transfer phenomena in nuclear systems and examines the critical contribution of this analysis to nuclear technology development. With a strong focus on system thermal hydraulics (SYS TH), the book provides a detailed, yet approachable, presentation of current approaches to reactor thermal hydraulic analysis, also considering the importance of this discipline for the design and operation of safe and efficient water-cooled and moderated reactors. Part One presents the background to nuclear thermal hydraulics, starting with a historical perspective, defining key terms, and considering thermal hydraulics requirements in nuclear technology. Part Two addresses the principles of thermodynamics and relevant target phenomena in nuclear systems. Next, the book focuses on nuclear thermal hydraulics modeling, covering the key areas of heat transfer and pressure drops, then moving on to an introduction to SYS TH and computational fluid dynamics codes. The final part of the book reviews the application of thermal hydraulics in nuclear technology, with chapters on V&V and uncertainty in SYS TH codes, the BEPU approach, and applications to new reactor design, plant lifetime extension, and accident analysis. This book is a valuable resource for academics, graduate students, and professionals studying the thermal hydraulic analysis of nuclear power plants and using SYS TH to demonstrate their safety and acceptability. - Contains a systematic and comprehensive review of current approaches to the thermal-hydraulic analysis of water-cooled and moderated nuclear reactors - Clearly presents the relationship between system level (top-down analysis) and component level phenomenology (bottom-up analysis) - Provides a strong focus on nuclear system thermal hydraulic (SYS TH) codes - Presents detailed coverage of the applications of thermal-hydraulics to demonstrate the safety and acceptability of nuclear power plants
Publisher: Woodhead Publishing
ISBN: 0081006799
Category : Technology & Engineering
Languages : en
Pages : 1200
Book Description
Thermal Hydraulics of Water-Cooled Nuclear Reactors reviews flow and heat transfer phenomena in nuclear systems and examines the critical contribution of this analysis to nuclear technology development. With a strong focus on system thermal hydraulics (SYS TH), the book provides a detailed, yet approachable, presentation of current approaches to reactor thermal hydraulic analysis, also considering the importance of this discipline for the design and operation of safe and efficient water-cooled and moderated reactors. Part One presents the background to nuclear thermal hydraulics, starting with a historical perspective, defining key terms, and considering thermal hydraulics requirements in nuclear technology. Part Two addresses the principles of thermodynamics and relevant target phenomena in nuclear systems. Next, the book focuses on nuclear thermal hydraulics modeling, covering the key areas of heat transfer and pressure drops, then moving on to an introduction to SYS TH and computational fluid dynamics codes. The final part of the book reviews the application of thermal hydraulics in nuclear technology, with chapters on V&V and uncertainty in SYS TH codes, the BEPU approach, and applications to new reactor design, plant lifetime extension, and accident analysis. This book is a valuable resource for academics, graduate students, and professionals studying the thermal hydraulic analysis of nuclear power plants and using SYS TH to demonstrate their safety and acceptability. - Contains a systematic and comprehensive review of current approaches to the thermal-hydraulic analysis of water-cooled and moderated nuclear reactors - Clearly presents the relationship between system level (top-down analysis) and component level phenomenology (bottom-up analysis) - Provides a strong focus on nuclear system thermal hydraulic (SYS TH) codes - Presents detailed coverage of the applications of thermal-hydraulics to demonstrate the safety and acceptability of nuclear power plants
Nuclear Science Abstracts
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 722
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 722
Book Description
Design Analysis of a Prepackaged Nuclear Power Plant (1000 EKW).: Reactor design analysis
Author:
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 294
Book Description
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 294
Book Description
Bibliographies of Interest to the Atomic Energy Program, 1962 Through 1966
Author: U.S. Atomic Energy Commission
Publisher:
ISBN:
Category : Bibliographical literature
Languages : en
Pages : 260
Book Description
Publisher:
ISBN:
Category : Bibliographical literature
Languages : en
Pages : 260
Book Description
Design for Reactor Core Safety in Nuclear Power Plants
Author: International Atomic Energy Agency
Publisher:
ISBN:
Category : Business & Economics
Languages : en
Pages : 72
Book Description
Covers the mechanical, chemical, thermal, hydraulic, neutronic and irradiation considerations important to the safe design of a nuclear reactor core. The core features of commonly used reactor types including light and heavy water reactors, as well as gas cooled reactors, are addressed.
Publisher:
ISBN:
Category : Business & Economics
Languages : en
Pages : 72
Book Description
Covers the mechanical, chemical, thermal, hydraulic, neutronic and irradiation considerations important to the safe design of a nuclear reactor core. The core features of commonly used reactor types including light and heavy water reactors, as well as gas cooled reactors, are addressed.
Structural Alloys for Nuclear Energy Applications
Author: Robert Odette
Publisher: Newnes
ISBN: 012397349X
Category : Technology & Engineering
Languages : en
Pages : 676
Book Description
High-performance alloys that can withstand operation in hazardous nuclear environments are critical to presentday in-service reactor support and maintenance and are foundational for reactor concepts of the future. With commercial nuclear energy vendors and operators facing the retirement of staff during the coming decades, much of the scholarly knowledge of nuclear materials pursuant to appropriate, impactful, and safe usage is at risk. Led by the multi-award winning editorial team of G. Robert Odette (UCSB) and Steven J. Zinkle (UTK/ORNL) and with contributions from leaders of each alloy discipline, Structural Alloys for Nuclear Energy Applications aids the next generation of researchers and industry staff developing and maintaining steels, nickel-base alloys, zirconium alloys, and other structural alloys in nuclear energy applications. This authoritative reference is a critical acquisition for institutions and individuals seeking state-of-the-art knowledge aided by the editors' unique personal insight from decades of frontline research, engineering and management. - Focuses on in-service irradiation, thermal, mechanical, and chemical performance capabilities. - Covers the use of steels and other structural alloys in current fission technology, leading edge Generation-IV fission reactors, and future fusion power reactors. - Provides a critical and comprehensive review of the state-of-the-art experimental knowledge base of reactor materials, for applications ranging from engineering safety and lifetime assessments to supporting the development of advanced computational models.
Publisher: Newnes
ISBN: 012397349X
Category : Technology & Engineering
Languages : en
Pages : 676
Book Description
High-performance alloys that can withstand operation in hazardous nuclear environments are critical to presentday in-service reactor support and maintenance and are foundational for reactor concepts of the future. With commercial nuclear energy vendors and operators facing the retirement of staff during the coming decades, much of the scholarly knowledge of nuclear materials pursuant to appropriate, impactful, and safe usage is at risk. Led by the multi-award winning editorial team of G. Robert Odette (UCSB) and Steven J. Zinkle (UTK/ORNL) and with contributions from leaders of each alloy discipline, Structural Alloys for Nuclear Energy Applications aids the next generation of researchers and industry staff developing and maintaining steels, nickel-base alloys, zirconium alloys, and other structural alloys in nuclear energy applications. This authoritative reference is a critical acquisition for institutions and individuals seeking state-of-the-art knowledge aided by the editors' unique personal insight from decades of frontline research, engineering and management. - Focuses on in-service irradiation, thermal, mechanical, and chemical performance capabilities. - Covers the use of steels and other structural alloys in current fission technology, leading edge Generation-IV fission reactors, and future fusion power reactors. - Provides a critical and comprehensive review of the state-of-the-art experimental knowledge base of reactor materials, for applications ranging from engineering safety and lifetime assessments to supporting the development of advanced computational models.