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Klappentext Corrosion is a major problem in nuclear reactors and nuclear fuel and waste management facilities! where the integrity of radioactive containment systems is required to hold firm under very stringent conditions and over extended periods of time. This book critically reviews the fundamental corrosion mechanisms! the systems and materials they affect! and the methods to accurately measure and model their incidence in critical plant environments. Inhaltsverzeichnis 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-aqueo...
