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Materials ageing and degradation in light water reactors: Mechanisms and managementEdited by K L Murty, North Carolina State University, USA
Woodhead Publishing Series in Energy No. 44
- 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
- provides a comprehensive review for nuclear power-plant operators, metallurgists, researchers, scientists and academics working in the field
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.
ISBN 0 85709 239 1
ISBN-13: 978 0 85709 239 7
February 2013
440 pages 234 x 156mm hardback
£150.00 / US$255.00 / €180.00
Usually dispatched within 24 hours
About the editor
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.
Titles which may also be of interest:
Understanding and mitigating ageing in nuclear power plants
Irradiation embrittlement of reactor pressure vessels (RPVs) in nuclear power plants
Nuclear corrosion science and engineering
Structural alloys for power plants
Creep-resistant steels
Electrochemistry in light water reactors
Contents
PART 1 FUNDAMENTAL AGEING ISSUES AND DEGRADATION MECHANISMS
PART 2 MATERIALS AGEING AND DEGRADATION IN PARTICULAR LIGHT WATER REACTOR (LWR) COMPONENTS
PART 3 MATERIALS MANAGEMENT STRATEGIES FOR LIGHT WATER REACTORS (LWRS)
PART 1 FUNDAMENTAL AGEING ISSUES AND DEGRADATION MECHANISMS
Overview of ageing and degradation issues in light water reactors (LWRs)
K L Murty, North Carolina State University, USA and K Ramaswamy, Bhabha Atomic Research Center, India
- Introduction
- Degradation mechanisms and materials ageing issues in nuclear steam supply systems (NSSS)
- Radiation effects
- Degradation mechanisms of specific nuclear reactor structures
- Conclusions
- References
Corrosion in pressurized water reactors (PWRs)
T Couvant, EDF R&D, France
- Introduction
- Pressurized water reactors and the main types of corrosion
- Major components experiencing corrosion
- Conclusion
- References
Creep deformation of materials in light water reactors (LWRs)
K L Murty, North Carolina State University, USA, S Gollapudi, Massachusetts Institute of Technology, USA, K Ramaswamy, Bhabha Atomic Research Center, India, M D Mathew, Indira Gandhi Center for Atomic Research, India and I Charit, University of Idaho, USA
- Introduction
- Standard creep equations
- Identifying the mechanisms of creep
- Rate controlling mechanisms and activation energy
- Transitions in creep mechanisms
- Modeling creep life: extrapolation of strain and rupture data
- Case studies illustrating the role other factors
- Creep of zirconium alloys used for LWR cladding
- References
PART 2 MATERIALS AGEING AND DEGRADATION IN PARTICULAR LIGHT WATER REACTOR (LWR) COMPONENTS
Properties of zirconium alloys and their applications in light water reactors (LWRs)
R B Adamson, Zircology Plus, USA and P Rudling, ANT International, Sweden
- Introduction
- Fuel assembly designs
- Effects of irradiation on zirconium alloys
- Mechanical properties of zirconium alloys
- Corrosion of zirconium alloys
- Dimensional stability of zirconium alloys
- Future trends and research needs
- Sources of further information
- Acknowledgement
- References
Performance and inspection of zirconium alloy fuel bundle components in light water reactors (LWRs)
P Rudling, ANT International, Sweden and R B Adamson, Zircology Plus, USA
- Introduction
- Materials performance during normal operational conditions
- Materials performance during accidents
- Materials performance during interim dry storage
- Inspection methods
- Future trends and research needs
- Source of further information and advice
- Acknowledgement
- References
Ageing of electric cables in light water reactors (LWRs)
H M Hashemian, Analysis and Measurement Services Corp, USA
- Introduction
- Cable degradation issues
- Analysis and assessment methods
- Residual life modeling
- Development and application of mitigation routes
- Sources of further information
- References
PART 3 MATERIALS MANAGEMENT STRATEGIES FOR LIGHT WATER REACTORS (LWRS)
Materials management strategies for pressurized water reactors (PWRs)
Y H Jeong and S S Hwang, Korea Atomic Energy Research Institute, Korea
- Introduction
- Materials management strategies
- Management techniques: development and application
- Case studies of management strategies
- References
Materials management strategies for VVER reactors
T J Katona, MVM Paks Nuclear Power Plant Ltd, Hungary
- Introduction
- Description of operating VVER reactors
- Ageing of the VVERs – plant operational experience
- Ensuring safety for a long-term operation
- Plant programmes credited for long-term operation
- Conclusion
- References
Materials-related problems faced by light water reactor (LWR) operators and corresponding research needs
S Ray and E Lahoda, Westinghouse Electric Company LLC, USA
- Introduction
- Fuel and cladding materials - the first fission barrier
- The primary system - the second fission barrier
- The containment structure - the final fission barrier
- Other nuclear reactor systems
- References