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Nuclear Corrosion Science and Engineering
- 1st Edition - February 21, 2012
- Editor: Damien Feron
- Language: English
- Hardback ISBN:9 7 8 - 1 - 8 4 5 6 9 - 7 6 5 - 5
- Paperback ISBN:9 7 8 - 0 - 0 8 - 1 0 1 6 3 4 - 3
- eBook ISBN:9 7 8 - 0 - 8 5 7 0 9 - 5 3 4 - 3
Corrosion of nuclear materials, i.e. the interaction between these materials and their environments, is a major issue for plant safety as well as for operation and economic… Read more
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Request a sales quoteCorrosion of nuclear materials, i.e. the interaction between these materials and their environments, is a major issue for plant safety as well as for operation and economic competitiveness. Understanding these corrosion mechanisms, the systems and materials they affect, and the methods to accurately measure their incidence is of critical importance to the nuclear industry. Combining assessment techniques and analytical models into this understanding allows operators to predict the service life of corrosion-affected nuclear plant materials, and to apply the most appropriate maintenance and mitigation options to ensure safe long term operation.
This book critically reviews the fundamental corrosion mechanisms that affect nuclear power plants and facilities. Initial sections introduce the complex field of nuclear corrosion science, with detailed chapters on the different types of both aqueous and non aqueous corrosion mechanisms and the nuclear materials susceptible to attack from them. This is complemented by reviews of monitoring and control methodologies, as well as modelling and lifetime prediction approaches. Given that corrosion is an applied science, the final sections review corrosion issues across the range of current and next-generation nuclear reactors, and across such nuclear applications as fuel reprocessing facilities, radioactive waste storage and geological disposal systems.
With its distinguished editor and international team of expert contributors, Nuclear corrosion science and engineering is an invaluable reference for nuclear metallurgists, materials scientists and engineers, as well as nuclear facility operators, regulators and consultants, and researchers and academics in this field.
This book critically reviews the fundamental corrosion mechanisms that affect nuclear power plants and facilities. Initial sections introduce the complex field of nuclear corrosion science, with detailed chapters on the different types of both aqueous and non aqueous corrosion mechanisms and the nuclear materials susceptible to attack from them. This is complemented by reviews of monitoring and control methodologies, as well as modelling and lifetime prediction approaches. Given that corrosion is an applied science, the final sections review corrosion issues across the range of current and next-generation nuclear reactors, and across such nuclear applications as fuel reprocessing facilities, radioactive waste storage and geological disposal systems.
With its distinguished editor and international team of expert contributors, Nuclear corrosion science and engineering is an invaluable reference for nuclear metallurgists, materials scientists and engineers, as well as nuclear facility operators, regulators and consultants, and researchers and academics in this field.
- Comprehensively reviews the fundamental corrosion mechanisms that affect nuclear power plants and facilities
- Chapters assess different types of both aqueous and non aqueous corrosion mechanisms and the nuclear materials susceptible to attack from them
- Considers monitoring and control methodologies, as well as modelling and lifetime prediction approaches
Nuclear metallurgists, materials scientists and engineers, nuclear facility operators, regulators and consultants, and researchers and academics in this field.
Contributor contact details
Woodhead Publishing Series in Energy
Preface
Part I: Introduction to corrosion in nuclear power applications
Chapter 1: Overview of corrosion engineering, science and technology
Abstract:
1.1 Introduction
1.2 Fundamentals of aqueous metallic corrosion
1.3 Forms of aqueous corrosion
1.4 Corrosion control
1.5 Metallurgical influences on corrosion
1.6 Mechanical influences on corrosion
1.9 Appendix: glossary of corrosion terms
Chapter 2: Overview of nuclear materials and nuclear corrosion science and engineering
Abstract:
2.1 Introduction
2.2 Nuclear environments
2.3 Zirconium alloys
2.4 Graphite
2.5 Carbon steels and low alloy steels
2.6 Stainless steels
2.7 Nickel alloys
2.8 Cobalt alloys
2.9 Other alloys and composites
2.10 Conclusions
Chapter 3: Understanding and mitigating corrosion in nuclear reactor systems
Abstract:
3.1 Introduction
3.2 Reactor coolant circuits
3.3 Primary coolant systems
3.4 Secondary coolant systems
3.5 Conclusion
Part II: Aqueous corrosion in nuclear power applications: fundamental science, materials and mechanisms
Chapter 4: General corrosion in nuclear reactor components and nuclear waste disposal systems
Abstract:
4.1 Introduction
4.2 Basic principles and mechanisms
4.3 Nuclear components subject to general corrosion: reactor operations
4.4 Nuclear components subject to general corrosion: back end of the fuel cycle
Chapter 5: Environmentally assisted cracking (EAC) in nuclear reactor systems and components
Abstract:
5.1 Introduction
5.2 Basic principles of environmentally assisted cracking (EAC)
5.3 Alloys and components exposed to environmentally assisted cracking (EAC) in the nuclear industry
5.4 Models and mechanisms of environmentally assisted cracking (EAC)
5.5 Future trends: from experimental approach to numerical simulations
Chapter 6: Irradiation assisted corrosion and stress corrosion cracking (IAC/IASCC) in nuclear reactor systems and components
Abstract:
6.1 Introduction
6.2 Irradiation effects on microchemistry and microstructure
6.3 Irradiation effects on water chemistry
6.4 Irradiation effects on corrosion and stress corrosion cracking (SCC): lab and plant data
6.5 Conclusions
Chapter 7: Flow accelerated corrosion (FAC) in nuclear power plant components
Abstract:
7.1 Introduction to flow accelerated corrosion (FAC)
7.2 General aspects of flow accelerated corrosion (FAC)
7.3 Understanding and modeling of flow accelerated corrosion (FAC)
7.4 Theoretical model
7.5 Systems and components susceptible to flow accelerated corrosion (FAC): maintenance programs and experience feedback
7.6 Conclusion and future trends for flow accelerated corrosion (FAC) management
Chapter 8: Microbiologically influenced corrosion (MIC) in nuclear power plant systems and components
Abstract:
8.1 Introduction
8.2 Biofilms and biofouling
8.3 Microbial corrosion of different materials
8.4 Industrial examples
8.5 Tools to study microbial corrosion
8.6 Protection against microbial corrosion
Part III: Non-aqueous corrosion in nuclear power applications: fundamental science, materials and mechanisms
Chapter 9: High-temperature oxidation in nuclear reactor systems
Abstract:
9.1 Introduction
9.2 General behaviour of reactions at high temperatures
9.3 Reactions with hot gases
9.4 Solid-state reactions
9.5 Mitigation
Chapter 10: Liquid metal corrosion in nuclear reactor and accelerator driven systems
Abstract:
10.1 Liquid metals as heat transfer fluids
10.2 General features of corrosion and mass transfer in liquid metal systems
10.3 Corrosion in liquid sodium systems
10.4 Corrosion in lithium systems
10.5 Corrosion in lead-lithium systems
10.6 Corrosion in liquid lead and lead-bismuth eutectic systems
10.7 Conclusions
10.8 Acknowledgements
Part IV: Corrosion monitoring and control in nuclear power applications
Chapter 11: Electrochemical techniques for monitoring and controlling corrosion in water-cooled nuclear reactor systems
Abstract:
11.1 Introduction
11.2 Properties of the environment
11.3 Sensors
11.4 Reference electrodes
11.5 Redox and corrosion potential sensors
11.6 Hydrogen and oxygen sensors
11.7 In-situ corrosion monitors
11.8 Future trends
11.10 List of abbreviations
Chapter 12: On line electrochemical monitoring in light water reactor (LWR) systems
Abstract:
12.1 Introduction
12.2 Measurements in boiling water reactors (BWRs)
12.3 Pressurized water reactor (PWR) primary system
12.4 Pressurized water reactor (PWR) secondary system
12.5 Conclusions
Chapter 13: Modelling corrosion in nuclear power plant systems
Abstract:
13.1 Introduction
13.2 Modelling techniques for corrosion: empirical and semi-empirical models
13.3 Other modelling techniques
Chapter 14: Lifetime prediction techniques for nuclear power plant systems
Abstract:
14.1 Introduction
14.2 Ageing management
14.3 Risk-informed inspection
14.4 Integrity assessment methods and lifetime calculations of reactor pressure vessel, piping and other load-bearing components
14.4.3 Fracture mechanics analysis procedures and tools
14.5 Ageing of concrete structures
14.6 Future trends
Part V: Corrosion issues in current nuclear reactors and applications
Chapter 15: Corrosion issues in pressurized water reactor (PWR) systems
Abstract:
15.1 Introduction
15.2 Primary circuits
15.3 Stress corrosion cracking (SCC)
15.4 Austenitic stainless steels – stress corrosion cracking (SCC)
15.5 Secondary circuits: steam generators
15.6 Secondary circuits: miscellaneous
15.7 Tertiary circuits, fire protection systems and auxiliary circuits
15.8 Monitoring, modelling and lifetime prediction methods
15.9 Corrosion control and mitigation options
15.10 Future trends
15.11 Conclusion
15.12 Acknowledgement
15.14 List of abbreviations
Chapter 16: Intergranular stress corrosion cracking (IGSCC) in boiling water reactors (BWRs)
Abstract:
16.1 Introduction
16.2 Intergranular stress corrosion cracking (IGSCC) in boiling water reactor (BWR) piping
16.3 Modeling and lifetime prediction methods for stainless steel
16.4 Modeling and lifetime prediction methods for nickel-base alloys
16.5 Mitigation of intergranular stress corrosion cracking (IGSCC) in boiling water reactors (BWRs)
16.6 Future trends
Chapter 17: Corrosion issues in pressurized heavy water reactor (PHWR/CANDU®) systems
Abstract:
17.1 Introduction
17.2 Overview of CANDU® materials degradation
17.3 Monitoring, modelling, mitigation and lifetime prediction
17.4 Future trends
17.5 Acknowledgements
Chapter 18: Corrosion issues in water-cooled water-moderated energetic reactor (WWER) systems
Abstract:
18.1 Introduction
18.2 Corrosion issues
18.3 Monitoring and corrosion control
18.4 Conclusions
18.5 Acknowledgments
18.7 Appendix: acronyms and abbreviations
Chapter 19: Corrosion issues in nuclear fuel reprocessing plants
Abstract:
19.1 Introduction
19.2 Corrosion mechanisms of austenitic stainless steels in nitric media used in reprocessing plants
19.3 Corrosion behaviour of zirconium in nitric media used in reprocessing plants
19.4 Future trends
19.5 Conclusion
Part VI: Corrosion issues in next generation nuclear reactors and advanced applications
Chapter 20: Corrosion issues in high temperature gas-cooled reactor (HTR) systems
Abstract:
20.1 Introduction
20.2 General high temperature reactor (HTR) plant description
20.3 Outline of the main corrosion issues specifically related to high temperature reactor (HTR) technology
20.4 High temperature corrosion of structural metallic alloys in the primary coolant He of a high temperature reactor (HTR)
20.5 Oxidation of different graphite materials used in high temperature reactor (HTR) systems
20.6 UO2/C interaction inside the tristructural-isotropic (TRISO) fuel
20.7 Corrosion studies on the pebble bed modular reactor (PBMR) spent fuel tank materials
20.8 Future trends
Chapter 21: Corrosion issues in sodium-cooled fast reactor (SFR) systems
Abstract:
21.1 Introduction
21.2 Core and structural materials for sodium-cooled fast reactors (SFRs)
21.3 Corrosion issues related to sodium-cooled fast reactors (SFRs)
21.4 Corrosion estimation for design
21.5 Conclusion
Chapter 22: Corrosion issues in lead-cooled fast reactor (LFR) and accelerator driven systems (ADS)
Abstract:
22.1 Introduction
22.2 Overview of corrosion in liquid lead alloys
22.3 Corrosion issues and reactor concepts
22.4 Corrosion control and monitoring and mitigation options
22.5 Modelling and lifetime prediction methods
22.6 Future trends
Chapter 23: Corrosion issues in molten salt reactor (MSR) systems
Abstract:
23.1 The development and operational experience of molten salt reactors (MSRs)
23.2 Corrosion processes in molten salts
23.3 Review of molten salt corrosion data
23.4 Monitoring, modeling and lifetime prediction methods
23.5 Material development and corrosion control
Chapter 24: Corrosion issues in supercritical water reactor (SCWR) systems
Abstract:
24.1 Introduction
24.2 Corrosion in supercritical water reactors (SCWRs)
24.3 Stress corrosion cracking (SCC) in supercritical water
24.4 Conclusion
Chapter 25: Corrosion issues in thermonuclear fusion reactors and facilities
Abstract:
25.1 Introduction
25.2 Corrosion issues for the international thermonuclear experimental reactor (ITER)
25.3 Corrosion issues for fusion power reactors
25.4 Corrosion issues for international fusion materials irradiation facility (IFMIF)
25.5 Modelling tools
25.6 Future trends
Chapter 26: Corrosion issues of radioactive waste packages in geological disposal systems
Abstract:
26.1 Introduction
26.2 Potential corrosion issues in waste packages
26.3 Experimental and modelling approaches to the corrosion behaviour of waste package constituents
26.4 Future trends and recommendations
26.6 Acknowledgements
Appendix: Corrosion issues in radioactive waste interim storage facilities
Index
- No. of pages: 1072
- Language: English
- Edition: 1
- Published: February 21, 2012
- Imprint: Woodhead Publishing
- Hardback ISBN: 9781845697655
- Paperback ISBN: 9780081016343
- eBook ISBN: 9780857095343
DF
Damien Feron
Damien Féron, CEA Saclay, France.
Affiliations and expertise
CEA Saclay, France.Read Nuclear Corrosion Science and Engineering on ScienceDirect