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Materials Ageing and Degradation in Light Water Reactors
Mechanisms and Management
- 1st Edition - February 18, 2013
- Editor: K. L. Murty
- Language: English
- Paperback ISBN:9 7 8 - 0 - 0 8 - 1 0 1 6 0 6 - 0
- Hardback ISBN:9 7 8 - 0 - 8 5 7 0 9 - 2 3 9 - 7
- eBook ISBN:9 7 8 - 0 - 8 5 7 0 9 - 7 4 5 - 3
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… Read more
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Request a sales quoteLight 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.
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
Researchers and practitioners in the nuclear power industry, process industry (chemical plants, petrochemical)and aerospace; Academics and researchers in nuclear engineering fields
Contributor contact details
Woodhead Publishing Series in Energy
Foreword
Preface
Chapter 1: Overview of ageing and degradation issues in light water reactors (LWRs)
1.1 Introduction
1.2 Degradation mechanisms and materials ageing issues in nuclear steam supply systems (NSSS)
1.3 Radiation effects
1.4 Degradation mechanisms of specific nuclear reactor structures
1.5 Conclusions
Chapter 2: Corrosion in pressurized water reactors (PWRs)
Abstract:
2.1 Introduction
2.2 Pressurized water reactors and the main types of corrosion
2.3 Major components experiencing corrosion
2.4 Conclusion
Chapter 3: Creep deformation of materials in light water reactors (LWRs)
Abstract:
3.1 Introduction
3.2 Standard creep equations
3.3 Identifying the mechanisms of creep
3.4 Rate controlling mechanisms and activation energy
3.5 Transitions in creep mechanisms
3.6 Modeling creep life: extrapolation of strain and rupture data
3.7 Case studies illustrating the role of other factors
3.8 Creep of zirconium alloys used for LWR cladding
Chapter 4: Properties of zirconium alloys and their applications in light water reactors (LWRs)
Abstract:
4.1 Introduction
4.2 Fuel assembly designs
4.3 Effects of irradiation on zirconium alloys
4.4 Mechanical properties of zirconium alloys
4.5 Corrosion of zirconium alloys
4.6 Dimensional stability of zirconium alloys
4.7 Future trends and research needs
4.8 Sources of further information
4.9 Acknowledgements
Chapter 5: Performance and inspection of zirconium alloy fuel bundle components in light water reactors (LWRs)
Abstract:
5.1 Introduction
5.2 Materials performance during normal operational conditions
5.3 Materials performance during accidents
5.4 Materials performance during interim dry storage
5.5 Inspection methods
5.6 Future trends and research needs
5.7 Sources of further information and advice
5.8 Acknowledgements
Chapter 6: Ageing of electric cables in light water reactors (LWRs)
6.1 Introduction
6.2 Cable degradation issues
6.3 Analysis and assessment methods
6.4 Residual life modeling
6.5 Development and application of cable ageing mitigation routes
Chapter 7: Materials management strategies for pressurized water reactors (PWRs)
Abstract:
7.1 Introduction
7.2 Materials management strategies
7.3 Management techniques: development and application
7.4 Case studies of management strategies
Chapter 8: Materials management strategies for VVER reactors
Abstract:
8.1 Introduction
8.2 Description of operating VVER reactors
8.3 Ageing of the VVERs – plant operational experience
8.4 Ensuring safety for a long-term operation
8.5 Plant programmes credited for long-term operation
8.6 Conclusion
Chapter 9: Materials-related problems faced by light water reactor (LWR) operators and corresponding research needs
Abstract:
9.1 Introduction
9.2 Fuel and cladding materials – the first fission barrier
9.3 The primary system – the second fission barrier
9.4 The containment structure – the final fission barrier
9.5 Other nuclear reactor systems
Index
- No. of pages: 440
- Language: English
- Edition: 1
- Published: February 18, 2013
- Imprint: Woodhead Publishing
- Paperback ISBN: 9780081016060
- Hardback ISBN: 9780857092397
- eBook ISBN: 9780857097453
KM
K. L. Murty
K. L. Murty is a professor of nuclear engineering and materials science at North Carolina State University, USA, and a Fellow of the American Nuclear Society and the American Society for Materials International. Professor Murty has extensive experience in the field and has published over 290 technical papers on related topics. He was the first recipient of the ANS Mishima Award for outstanding research in nuclear materials.
Affiliations and expertise
North Carolina State University, USARead Materials Ageing and Degradation in Light Water Reactors on ScienceDirect