Author:
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 896
Book Description
Proceedings of the ... International Conference on Nuclear Engineering
Proceedings of the 12th International Conference on Nuclear Engineering ICONE-12
Author: ASME. Nuclear Engineering Division
Publisher:
ISBN: 9780791846889
Category :
Languages : en
Pages : 888
Book Description
Publisher:
ISBN: 9780791846889
Category :
Languages : en
Pages : 888
Book Description
Proceedings of the ASME Pressure Vessels and Piping Conference--2006: Codes and standards
Stress Corrosion Cracking in Light Water Reactors
Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201172105
Category : Technology & Engineering
Languages : en
Pages : 0
Book Description
Provides general descriptions of degradation mechanisms of different types of stress corrosion cracking (SCC) which are concerned with systems, structures and components in PWRs and BWRs. This publication includes examples of good practices in preventing, mitigating and repairing SCC damage and summarizes research and development programmes.
Publisher:
ISBN: 9789201172105
Category : Technology & Engineering
Languages : en
Pages : 0
Book Description
Provides general descriptions of degradation mechanisms of different types of stress corrosion cracking (SCC) which are concerned with systems, structures and components in PWRs and BWRs. This publication includes examples of good practices in preventing, mitigating and repairing SCC damage and summarizes research and development programmes.
Stress Corrosion Cracking of Nickel Based Alloys in Water-cooled Nuclear Reactors
Author: Damien Feron
Publisher: Woodhead Publishing
ISBN: 0081000626
Category : Technology & Engineering
Languages : en
Pages : 386
Book Description
Stress Corrosion Cracking of Nickel Based Alloys in Water-Cooled Nuclear Reactors: The Coriou Effect presents the latest information on brittle failure of metals in corrosive chemical environments under the influence of tensile stresses. Nickel alloys are more resistant to SCC as well as high temperatures and have been widely used in more challenging environments such as nuclear power plants. However, these alloys can suffer SCC under certain conditions, resulting in component failure. A key figure in understanding the mechanisms of SCC in nickel alloys in water-cooled nuclear reactors is Henri Coriou of the CEA, France's leading center for nuclear research. This book assesses his work in the context of the latest research on SCC in nickel alloys in nuclear power plants. - Up-to-date reviews of recent research findings from leading experts in the field - Authoritative and comprehensively reviewed by the Working Party 4 on Nuclear Corrosion - Showcases the excellent quality and technical accomplishments of Henri Coriou and CEA
Publisher: Woodhead Publishing
ISBN: 0081000626
Category : Technology & Engineering
Languages : en
Pages : 386
Book Description
Stress Corrosion Cracking of Nickel Based Alloys in Water-Cooled Nuclear Reactors: The Coriou Effect presents the latest information on brittle failure of metals in corrosive chemical environments under the influence of tensile stresses. Nickel alloys are more resistant to SCC as well as high temperatures and have been widely used in more challenging environments such as nuclear power plants. However, these alloys can suffer SCC under certain conditions, resulting in component failure. A key figure in understanding the mechanisms of SCC in nickel alloys in water-cooled nuclear reactors is Henri Coriou of the CEA, France's leading center for nuclear research. This book assesses his work in the context of the latest research on SCC in nickel alloys in nuclear power plants. - Up-to-date reviews of recent research findings from leading experts in the field - Authoritative and comprehensively reviewed by the Working Party 4 on Nuclear Corrosion - Showcases the excellent quality and technical accomplishments of Henri Coriou and CEA
Hot Cracking Phenomena in Welds III
Author: John Lippold
Publisher: Springer Science & Business Media
ISBN: 3642168647
Category : Technology & Engineering
Languages : en
Pages : 439
Book Description
This is the third in a series of compendiums devoted to the subject of weld hot cracking. It contains 22 papers presented at the 3rd International Hot Cracking Workshop in Columbus, Ohio USA in March 2010. In the context of this workshop, the term “hot cracking” refers to elevated temperature cracking associated with either the weld metal or heat-affected zone. These hot cracking phenomena include weld solidification cracking, HAZ and weld metal liquation cracking, and ductility-dip cracking. The book is divided into three major sections based on material type; specifically aluminum alloys, steels, and nickel-base alloys. Each of these sections begins with a keynote paper from prominent researchers in the field: Dr. Sindo Kou from the University of Wisconsin, Dr. Thomas Böllinghaus from BAM and the University of Magdeburg, and Dr. John DuPont from Lehigh University. The papers contained within include the latest insight into the mechanisms associated with hot cracking in these materials and methods to prevent cracking through material selection, process modification, or other means. The three Hot Cracking Phenomena in Welds compendiums combined contain a total of 64 papers and represent the best collection of papers on the topic of hot cracking ever assembled.
Publisher: Springer Science & Business Media
ISBN: 3642168647
Category : Technology & Engineering
Languages : en
Pages : 439
Book Description
This is the third in a series of compendiums devoted to the subject of weld hot cracking. It contains 22 papers presented at the 3rd International Hot Cracking Workshop in Columbus, Ohio USA in March 2010. In the context of this workshop, the term “hot cracking” refers to elevated temperature cracking associated with either the weld metal or heat-affected zone. These hot cracking phenomena include weld solidification cracking, HAZ and weld metal liquation cracking, and ductility-dip cracking. The book is divided into three major sections based on material type; specifically aluminum alloys, steels, and nickel-base alloys. Each of these sections begins with a keynote paper from prominent researchers in the field: Dr. Sindo Kou from the University of Wisconsin, Dr. Thomas Böllinghaus from BAM and the University of Magdeburg, and Dr. John DuPont from Lehigh University. The papers contained within include the latest insight into the mechanisms associated with hot cracking in these materials and methods to prevent cracking through material selection, process modification, or other means. The three Hot Cracking Phenomena in Welds compendiums combined contain a total of 64 papers and represent the best collection of papers on the topic of hot cracking ever assembled.
Nuclear Energy Basic Principles
Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201126085
Category : Business & Economics
Languages : en
Pages : 0
Book Description
Describes the rationale and vision for the peaceful use of nuclear energy. The publication identifies the basic principles that nuclear energy systems must satisfy to fulfil their promise of meeting growing global energy demands.
Publisher:
ISBN: 9789201126085
Category : Business & Economics
Languages : en
Pages : 0
Book Description
Describes the rationale and vision for the peaceful use of nuclear energy. The publication identifies the basic principles that nuclear energy systems must satisfy to fulfil their promise of meeting growing global energy demands.
Stress-corrosion Cracking
Author: Russell H. Jones
Publisher: ASM International(OH)
ISBN:
Category : Science
Languages : en
Pages : 466
Book Description
Details the many conditions under which stress-corrosion cracking (SCC) can occur, the parameters which control SCC, and the methodologies for mitigating and testing for SCC, plus information on mechanisms of SCC with experimental data on a variety of materials. Contains information about environmen
Publisher: ASM International(OH)
ISBN:
Category : Science
Languages : en
Pages : 466
Book Description
Details the many conditions under which stress-corrosion cracking (SCC) can occur, the parameters which control SCC, and the methodologies for mitigating and testing for SCC, plus information on mechanisms of SCC with experimental data on a variety of materials. Contains information about environmen
Materials Ageing and Degradation in Light Water Reactors
Author: K L Murty
Publisher: Elsevier
ISBN: 0857097458
Category : Technology & Engineering
Languages : en
Pages : 441
Book Description
Light water reactors (LWRs) are the predominant class of nuclear power reactors in operation today; however, ageing and degradation can influence both their performance and lifetime. Knowledge of these factors is therefore critical to safe, continuous operation. Materials ageing and degradation in light water reactors provides a comprehensive guide to prevalent deterioration mechanisms, and the approaches used to handle their effects.Part one introduces fundamental ageing issues and degradation mechanisms. Beginning with an overview of ageing and degradation issues in LWRs, the book goes on to discuss corrosion in pressurized water reactors and creep deformation of materials in LWRs. Part two then considers materials' ageing and degradation in specific LWR components. Applications of zirconium alloys in LWRs are discussed, along with the ageing of electric cables. Materials management strategies for LWRs are then the focus of part three. Materials management strategies for pressurized water reactors and VVER reactors are considered before the book concludes with a discussion of materials-related problems faced by LWR operators and corresponding research needs.With its distinguished editor and international team of expert contributors, Materials ageing and degradation in light water reactors is an authoritative review for anyone requiring an understanding of the performance and durability of this type of nuclear power plant, including plant operators and managers, nuclear metallurgists, governmental and regulatory safety bodies, and researchers, scientists and academics working in this area. - Introduces the fundamental ageing issues and degradation mechanisms associated with this class of nuclear power reactors - Considers materials ageing and degradation in specific light water reactor components, including properties, performance and inspection - Chapters also focus on material management strategies
Publisher: Elsevier
ISBN: 0857097458
Category : Technology & Engineering
Languages : en
Pages : 441
Book Description
Light water reactors (LWRs) are the predominant class of nuclear power reactors in operation today; however, ageing and degradation can influence both their performance and lifetime. Knowledge of these factors is therefore critical to safe, continuous operation. Materials ageing and degradation in light water reactors provides a comprehensive guide to prevalent deterioration mechanisms, and the approaches used to handle their effects.Part one introduces fundamental ageing issues and degradation mechanisms. Beginning with an overview of ageing and degradation issues in LWRs, the book goes on to discuss corrosion in pressurized water reactors and creep deformation of materials in LWRs. Part two then considers materials' ageing and degradation in specific LWR components. Applications of zirconium alloys in LWRs are discussed, along with the ageing of electric cables. Materials management strategies for LWRs are then the focus of part three. Materials management strategies for pressurized water reactors and VVER reactors are considered before the book concludes with a discussion of materials-related problems faced by LWR operators and corresponding research needs.With its distinguished editor and international team of expert contributors, Materials ageing and degradation in light water reactors is an authoritative review for anyone requiring an understanding of the performance and durability of this type of nuclear power plant, including plant operators and managers, nuclear metallurgists, governmental and regulatory safety bodies, and researchers, scientists and academics working in this area. - Introduces the fundamental ageing issues and degradation mechanisms associated with this class of nuclear power reactors - Considers materials ageing and degradation in specific light water reactor components, including properties, performance and inspection - Chapters also focus on material management strategies
Proceedings of the Second International Symposium on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors
Author: National Association of Corrosion Engineers
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 680
Book Description
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 680
Book Description