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Informationen zum Autor 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.
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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
