Cover -- Nuclear corrosion science and engineering -- Copyright -- Contents -- Contributor contact details -- Woodhead Publishing Series in Energy -- Preface -- Part I Introduction to corrosion in nuclear power applications -- 1 Overview of corrosion engineering, science and technology -- 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 -- 1.7 Sources of further information and advice -- 1.8 References -- 1.9 Appendix: glossary of corrosion terms -- 2 Overview of nuclear materials and nuclear corrosion science and engineering -- 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 -- 2.11 Bibliography -- 3 Understanding and mitigating corrosion in nuclear reactor systems -- 3.1 Introduction -- 3.2 Reactor coolant circuits -- 3.3 Primary coolant systems -- 3.4 Secondary coolant systems -- 3.5 Conclusion -- 3.6 References -- Part II Aqueous corrosion in nuclear power applications: fundamental science, materials and mechanisms -- 4 General corrosion in nuclear reactor components and nuclear waste disposal systems -- 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 -- 4.5 Sources of further information and advice -- 4.6 References -- 5 Environmentally assisted cracking (EAC) in nuclear reactor systems and components -- 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 -- 5.6 Sources of further information and advice -- 5.7 References -- 6 Irradiation assisted corrosion and stress corrosion cracking (IAC/IASCC) in nuclear reactor systems and components -- 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 -- 6.6 References -- 7 Flow accelerated corrosion (FAC) in nuclear power plant components -- 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 -- 7.7 Sources of further information and advice -- 7.8 References -- 8 Microbiologically influenced corrosion (MIC) in nuclear power plant systems and components -- 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 -- 8.7 References -- Part III Non-aqueous corrosion in nuclear power applications: fundamental science, materials and mechanisms -- 9 High-temperature oxidation in nuclear reactor systems -- 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 -- 9.6 Sources of further information -- 9.7 References -- 10 Liquid metal corrosion in nuclear reactor and accelerator driven systems -- 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 -- 10.9 References -- Part IV Corrosion monitoring and control in nuclear power applications -- 11 Electrochemical techniques for monitoring and controlling corrosion in water-cooled nuclear reactor systems -- 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 -- 11.9 References -- 11.10 List of abbreviations -- 12 On line electrochemical monitoring in light water reactor (LWR) systems -- 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 -- 12.6 References -- 13 Modelling corrosion in nuclear power plant systems -- 13.1 Introduction -- 13.2 Modelling techniques for corrosion: empirical and semi-empirical models -- 13.3 Other modelling techniques -- 13.4 References -- 14 Lifetime prediction techniques for nuclear power plant systems -- 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 -- 14.5 Ageing of concrete structures.

14.6 Future trends -- 14.7 References -- Part V Corrosion issues in current nuclear reactors and applications -- 15 Corrosion issues in pressurized water reactor (PWR) systems -- 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 -- 15.13 References -- 15.14 List of abbreviations -- 16 Intergranular stress corrosion cracking(IGSCC) in boiling water reactors (BWRs) -- 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 -- 16.7 Sources of further information and advice -- 16.8 References -- 17 Corrosion issues in pressurized heavy water reactor (PHWR/CANDU®) systems -- 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 -- 17.6 References -- 18 Corrosion issues in water-cooled water-moderated energetic reactor (WWER) systems -- 18.1 Introduction -- 18.2 Corrosion issues -- 18.3 Monitoring and corrosion control -- 18.4 Conclusions -- 18.5 Acknowledgments -- 18.6 References -- 18.7 Appendix: acronyms and abbreviations -- 19 Corrosion issues in nuclear fuel reprocessing plants.

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 -- 19.6 References -- Part VI Corrosion issues in next generation nuclear reactors and advanced applications -- 20 Corrosion issues in high temperature gas-cooled reactor (HTR) systems -- 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 tristructuralisotropic (TRISO) fuel -- 20.7 Corrosion studies on the pebble bed modular reactor (PBMR) spent fuel tank materials -- 20.8 Future trends -- 20.9 References -- 21 Corrosion issues in sodium-cooled fast reactor (SFR) systems -- 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 -- 21.6 References -- 22 Corrosion issues in lead-cooled fast reactor (LFR) and accelerator driven systems (ADS) -- 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 -- 22.7 Sources of further information and advice -- 22.8 References -- 23 Corrosion issues in molten salt reactor (MSR) systems.

23.1 The development and operational experience of molten salt reactors (MSRs).