Understanding and Mitigating Ageing in Nuclear Power Plants - Materials and Operational Aspects of Plant Life Management (PLiM)

This book reviews the ageing-degradation mechanisms of materials used in nuclear power plant structures, systems and components, their relevant analysis and mitigation paths, and reactor-type specific plant life management (PLiM) practices. Obsolescence and other less obvious ageing-related aspects...

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Bibliographic Details
Main Author Tipping, Philip G.
Format eBook Book
LanguageEnglish
Published Oxford Woodhead Publishing 2010
Woodhead publishing
Elsevier Science & Technology
Edition1
SeriesWoodhead publishing series in energy
Subjects
Electrical & Power Engineering
Electrical Safety
Industrial Safety
Materials
Nuclear power plants
Nuclear reactors - Safety measures
Safety & Industrial Hygiene
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Table of Contents:
  • Title Page Executive Summary Table of Contents 1. Introduction to Nuclear Energy, and Materials and Operational Aspects of Nuclear Power Plants 2. Key Elements and Principles of Nuclear Power Plant Life Management (PLiM) for Current and Long-Term Operation 3. Safety Regulations for Nuclear Power Plant Life Management and Licence Renewal 4. Probabilistic and Deterministic Safety Assessment Methods for Nuclear Power Plant Life Management 5. Assessing the Socio-Economic Impacts of Ageing and Plant Life Management (AM-PLiM) Programmes for Long-Term Operation (LTO) of Nuclear Power Plants (NPPs) 6. Failure Prevention and Analysis in Nuclear Power Plant Systems, Structures and Components (SSC): A Holistic Approach 7. Impact of Operational Loads and Creep, Fatigue and Corrosion Interactions on Nuclear Power Plant Systems, Structures and Components (SSC) 8. Microstructure Evolution of Irradiated Structural Materials in Nuclear Power Plants 9. Stress Corrosion Cracking (SCC) of Austenitic Stainless Steels in High Temperature Light Water Reactor (LWR) Environments 10. Void Swelling and Irradiation Creep in Light Water Reactor (LWR) Environments 11. Irradiation Hardening and Materials Embrittlement in Light Water Reactor (LWR) Environments 12. Reactor Pressure Vessel (RPV) Annealing and Mitigation in Nuclear Power Plants 13. Characterization Techniques for Assessing Irradiated and Ageing Materials in Nuclear Power Plant Systems, Structures and Components (SSC) 14. On-Line and Real-Time Corrosion Monitoring Techniques of Metals and Alloys in Nuclear Power Plants and Laboratories 15. Multi-Scale Modelling of Irradiation Effects in Nuclear Power Plant Materials 16. Development and Application of Instrumentation and Control (I&C) Components in Nuclear Power Plants (NPPs) 17. Development and Application of Nano-Structured Materials in Nuclear Power Plants 18. Plant Life Management (PLiM) Practices for Pressurized Light Water Reactors (PWR) 19. Plant Life Management (PLiM) Practices for Water-Cooled Water-Moderated Nuclear Reactors (WWERs) 20. Plant Life Management (PLiM) Practices for Boiling Water Nuclear Reactors (BWR): Japanese Experience 21. Plant Life Management (PLiM) Practices for Pressurised Heavy Water Nuclear Reactors (PHWR) 22. Plant Life Management (PLiM) Practices for Sodium Cooled Fast Neutron Spectrum Nuclear Reactors (SFRs) 23. Plant Life Management (PLiM) Practices for Gas-Cooled, Graphite-Moderated Nuclear Reactors: UK Experience 24. Outlook for Nuclear Power Plant Life Management (PLiM) Practices - Summary, Conclusions, Recommendations Index
  • Cover -- Understanding and mitigating ageing in nuclear power plants: Materials and operational aspects of plant life management (PLiM) -- Copyright -- Contents -- Contributor contact details -- Woodhead Publishing Series in Energy -- Foreword -- Executive summary -- Overview of the book -- Overview of Part I -- Overview of Part II -- Overview of Part III -- Overview of Part IV -- Concluding remarks: Quo vadis nuclear power? -- Acknowledgements -- Part I Introduction to plant life management (PLiM), safety regulation and economics of nuclear power plants -- 1 Introduction to nuclear energy, and materials and operational aspects of nuclear power plants -- 1.1 Introduction -- 1.2 Age as a relative term -- 1.3 The importance of nuclear energy -- 1.4 Learning from experience to continually improve safety in nuclear power plants (NPPs) -- 1.5 Global situation of the status of installed nuclear power in 2010 -- 1.6 The importance of keeping nuclear power plants (npps) operating safely and reliably -- 1.7 Political and climate change issues and disposal of radioactive waste -- 1.8 Energy resources: a comparison -- 1.9 Further ageing aspects in nuclear power plants (NPPs) -- 1.10 Historical evolution of nuclear power and some materials aspects -- 1.11 Overview of two important materials issues in older design nuclear power plants (npps) -- 1.12 Conclusions -- 1.13 Sources of further information -- 1.14 References -- 2 Key elements and principles of nuclear power plant life management (PLiM) for current and long-term operation -- 2.1 Introduction -- 2.2 Nuclear power plant ageing terminology and associated definitions -- 2.3 Overview of ageing and its effects in nuclear power plants -- 2.4 Overview of systems, structures and components (ssc) safety classes
  • 2.5 Setting up and scoping ageing degradation and surveillence programmmes in nuclear power plants (NPPs) -- 2.6 S afety culture and human factors and knowledge management -- 2.7 Trends and issues in nuclear power plant (NPP) life management -- 2.8 Past, current and future nuclear power plant (NPP) concepts and designs -- 2.9 Conclusions -- 2.10 Sources of further information -- 2.11 Acknowledgements -- 2.12 References -- 3 Safety regulations for nuclear power plant life management and licence renewal -- 3.1 Introduction -- 3.2 Safety review/licence renewal -- 3.3 Surveillance, operation and maintenance programmes -- 3.4 Integration of plant life management -- 3.5 Ageing degradation mechanisms, and timelimited structures, systems and components -- 3.6 Main areas of concern for plant designers, operators and regulators -- 3.7 Future trends -- 3.8 References -- 4 Probabilistic and deterministic safety assessment methods for nuclear power plant life management -- 4.1 Introduction - plant safety assessment in a plant life management (PLiM) framework -- 4.2 The plant life management (PLiM) problem - definitions and selected experience cases -- 4.3 A unified proposal for a plant life management (PLiM) model integrating maintenance optimization -- 4.4 Probabilistic safety assessment of components and systems -- 4.5 Impact of ageing effects at system and plant level -- 4.6 Conclusions -- 4.7 References -- 5 Assessing the socio-economic impacts of ageing and plant life management (AM-PLiM) programmes for long-term operation (LTO) of nuclear power plants (NPPs) -- 5.1 Nuclear power as part of the global energy mix: energy demand, environmental issues and manpower -- 5.2 Aspects of current and future nuclear fuel supply and its impact on the viability of nuclear power -- 5.3 Economic overview of the nuclear power plant (NPP) lifecycle
  • 5.4 Cost drivers of nuclear power plant (NPP) operation -- 5.5 Basic economic requirements for sustainable operation of nuclear power plants (NPPs) -- 5.6 Assessing the costs and economics of nuclear power plant (NPP) operation and the impact of ageing and plant life management (AM-PLiM) programmes for long-term operation (LTO) -- 5.7 Conclusions -- 5.8 Sources of further information and advice -- 5.9 Acknowledgements -- 5.10 References -- Part II Ageing degradation of irradiated materials in nuclear power plant systems, structures and components (SSC): mechanisms, effects and mitigation techniques -- 6 Failure prevention and analysis in nuclear power plant systems, structures and components (SSC): a holistic approach -- 6.1 Introduction -- 6.2 Reducing failure probability and consequences thereof in nuclear power plant (NPP) systems, structures and components (SSCs) -- 6.3 Latent failure conditions (LFCs) and failure terminology -- 6.4 Holistic approach to analysing nuclear power plant systems, structures and components (npp ssc) failure events -- 6.5 Discussion -- 6.6 Conclusions -- 6.7 Sources of further information -- 6.8 References -- 7 Impact of operational loads and creep, fatigue and corrosion interactions on nuclear power plant systems, structures and components (SSC) -- 7.1 Introduction -- 7.2 Nuclear power plant (NPP) equipment materials -- 7.3 Medium and corrosion -- 7.4 Stress-corrosion cracking -- 7.5 Evaluation of impact of thermo-mechanical loading on strength of equipment materials -- 7.6 Equipment condition monitoring, prediction and testing -- 7.7 Conclusions and future trends -- 7.8 Acknowledgements -- 7.9 References and further reading -- 8 Microstructure evolution of irradiated structural materials in nuclear power plants -- 8.1 Introduction -- 8.2 Structures and materials affected -- 8.3 Environmental and other stressors
  • 11.7 Detection and measurement of irradiation hardening and embrittlement -- 11.8 Conclusions -- 11.9 Sources of further information and advice -- 11.10 References -- 12 Reactor pressure vessel (RPV) annealing and mitigation in nuclear power plants -- 12.1 Introduction -- 12.2 Structures and materials affected -- 12.3 Main mitigation measures -- 12.4 Mitigation mechanisms including microstructure changes -- 12.5 Application of research and operational experience to the practical solution of problems -- 12.6 Conclusions -- 12.7 Sources of further information -- 12.8 References -- Part III Analysis of nuclear power plant materials, and application of advanced systems, structures and components (SSC) -- 13 Characterization techniques for assessing irradiated and ageing materials in nuclear power plant systems, structures and components (SSC) -- 13.1 Introduction -- 13.2 Non-destructive techniques -- 13.3 Destructive techniques -- 13.4 Recent advances, future trends and new techniques -- 13.5 References -- 14 On-line and real-time corrosion monitoring techniques of metals and alloys in nuclear power plants and laboratories -- 14.1 Introduction -- 14.2 General corrosion monitoring -- 14.3 Localized corrosion monitoring -- 14.4 Electrochemical potential (ECP) monitoring -- 14.5 Conclusion -- 14.6 Acknowledgements -- 14.7 References -- 15 Multi-scale modelling of irradiation effects in nuclear power plant materials -- 15.1 Introduction -- 15.2 An overview of radiation effects -- 15.3 Multi-scale modelling -- 15.4 Nuclear- and atomic-level interactions -- 15.5 Atomic-level modelling -- 15.6 Microstructure evolution modelling -- 15.7 Mechanical property modelling -- 15.8 Example of application: the PERFECT example -- 15.9 Discussion -- 15.10 Conclusion -- 15.11 Acknowledgements -- 15.12 References
  • 16 Development and application of instrumentation and control (I&amp
  • 8.4 Changes in the microstructure and degradation mechanisms -- 8.5 Mitigation paths -- 8.6 Application of research and operational experience to the practical solution of problems -- 8.7 Acknowledgements -- 8.8 Definitions -- 8.9 Sources of further information and advice -- 8.10 References -- 9 Stress corrosion cracking (SCC) of austenitic stainless steels in high temperature light water reactor (LWR) environments -- 9.1 Introduction -- 9.2 Historical problems and structures affected -- 9.3 Stress corrosion cracking (SCC) dependencies - introduction -- 9.4 Stress corrosion cracking (SCC) dependencies - materials and water chemistry -- 9.5 Stress corrosion cracking (SCC) dependencies - cold work, stress intensity factor and irradiation -- 9.6 Stress corrosion cracking (SCC) dependencies - miscellaneous -- 9.7 Mechanism of stress corrosion cracking (SCC) -- 9.8 Stress corrosion cracking (SCC) mitigation -- 9.9 Prediction of stress corrosion cracking (SCC) and irradiation assisted stress corrosion cracking (IASCC) -- 9.10 Future trends -- 9.11 Sources of further information and advice -- 9.12 References -- 10 Void swelling and irradiation creep in light water reactor (LWR) environments -- 10.1 Introduction to void swelling and irradiation creep -- 10.2 Potential for swelling and irradiation creep in light water cooled reactors (LWRs) -- 10.3 Predictions of void swelling and associated uncertainties -- 10.4 Potential swelling/creep consequences -- 10.5 Second-order effects associated with or concurrent with void swelling -- 10.6 Conclusion -- 10.7 References -- 11 Irradiation hardening and materials embrittlement in light water reactor (LWR) environments -- 11.1 Introduction -- 11.2 Irradiation conditions -- 11.3 Nature of radiation damage -- 11.4 Irradiation hardening and embrittlement -- 11.5 Main factors -- 11.6 Predictive formulae