Materials and Water Chemistry for Supercritical Water-cooled Reactors (Woodhead Publishing Series in Energy)
معرفی کتاب «Materials and Water Chemistry for Supercritical Water-cooled Reactors (Woodhead Publishing Series in Energy)» نوشتهٔ David Guzonas, Radek Novotny, S. Pentilla, Aki Toivonen, Wenyue Zheng، منتشرشده توسط نشر Woodhead Publishing در سال 2017. این کتاب در فرمت pdf، زبان انگلیسی ارائه شده است.
Materials and Water Chemistry for Supercritical Water-cooled Reactors is unique in that it brings together materials __and__ water chemistry, their interrelationship, the historical perspective and their application to SCWR conceptual design. Written by world’s leading experts, all active in the area of materials and chemistry R&D in support of GEN IV SCWR, this book presents for the first time a comprehensive reference on these topics, and in particular, how these data relate to the SCWR design itself. This book is an essential text for researchers in the areas of supercritical water-cooled reactor materials and chemistry, working in industry or academia. It will also give newcomers to the field a survey of all of the available literature and a clear understanding of how these studies relate to the design of the SCWR concept. The material presented is at a specialist’s level in materials or corrosion science, or in water chemistry of power plants. * Provides comprehensive coverage of the chemistry and materials of SCWR * Presents the latest research and results condensed into one book * Covers the differences in use of SCW in nuclear reactors and fossil plants, and the resulting differences in materials requirements Cover Related titles Materials and Water Chemistry for Supercritical Water-cooled Reactors Copyright Acknowledgements List of abbreviations 1. Introduction 1.1 Early efforts 1.2 Recent developments 1.2.1 Synergies 1.3 Supercritical water-cooled reactor materials requirements 1.3.1 Candidate materials 1.4 Summary References 2. Experimental methodologies 2.1 Test facilities for corrosion and environmentally assisted cracking studies 2.2 Test specimens 2.2.1 Galvanic effects 2.3 Corrosion rate measurements 2.3.1 Surface finish 2.3.2 Weight gain versus weight loss 2.3.2.1 Reproducibility 2.3.3 Electrochemical methods 2.3.4 Other in situ analyses 2.4 Measurements of thermodynamic properties 2.5 Stress corrosion cracking 2.6 Testing under irradiated conditions 2.6.1 Materials testing 2.6.2 Water radiolysis studies References 3. Radiation effects and mechanical properties 3.1 Primary radiation damage 3.2 Effects on mechanical properties 3.2.1 Hardening 3.2.2 Ductility 3.2.3 Irradiation-assisted stress corrosion cracking 3.2.4 Void swelling 3.3 Effects on microchemistry: radiation-induced segregation 3.4 Creep 3.4.1 Introduction 3.4.2 Predicting creep 3.4.3 Irradiation-assisted creep 3.5 Microstructural instability 3.5.1 Microstructural instability due to high temperature exposure 3.5.2 Formation of precipitates due to radiation exposure 3.6 Modelling References 4. Water chemistry 4.1 Introduction 4.1.1 What is supercritical water? 4.2 Feedwater chemistry 4.2.1 Transport of corrosion products and other impurities 4.2.2 Transport of other impurities to the core 4.3 Activity transport 4.3.1 Activation of in-core materials 4.3.2 Defected fuel in a supercritical water-cooled reactor 4.3.2.1 Plant experience and experimental data Noble gases and iodines Fuel leaching tests 4.4 Water radiolysis 4.4.1 Approaches to modelling 4.4.1.1 Microscopic models 4.4.1.2 Semiempirical modelling 4.4.1.3 Large-scale loop or in-reactor studies 4.5 Chemistry control in a supercritical water-cooled reactor 4.6 Molecular dynamics simulations References 5. Corrosion 5.1 Introduction 5.1.1 Performance criteria 5.2 Alloy composition 5.2.1 Zr-based alloys 5.2.2 Ti-based alloys 5.3 Effects of key parameters 5.3.1 Temperature 5.3.2 Surface finish and grain size 5.3.3 Water chemistry 5.3.3.1 pH 5.3.3.2 Dissolved oxygen 5.3.3.3 Supercritical water pressure/density Near-critical region High T region 5.3.4 Flow rate 5.3.5 Heat transfer 5.3.6 Ageing 5.3.7 Irradiation 5.4 Oxide morphology 5.4.1 Ferritic–martensitic steels 5.4.2 Austenitic steels 5.4.3 Ni-based alloys 5.4.4 Coatings 5.5 Oxide growth kinetics 5.6 Mechanisms and modelling 5.6.1 Empirical and phenomenological models 5.6.2 Deterministic models References 6. Environmentally assisted cracking 6.1 Introduction 6.2 Effects of key variables 6.2.1 Environmental factors 6.2.1.1 Temperature 6.2.1.1.1 Near-critical region – the effect of supercritical water density 6.2.1.1.2 High Temperature Behaviour 6.2.1.2 Water chemistry 6.2.2 Material factors 6.2.3 Mechanical factors 6.2.3.1 Irradiation factors 6.3 Mechanisms and modelling References Index A B C D E F G H I J L M N O P R S T U V W Y Z Back Cover Annotation Materials and Water Chemistry for Supercritical Water-cooled Reactors is unique in that it brings together materials and water chemistry, their interrelationship, the historical perspective and their application to SCWR conceptual design. Written by world's leading experts, all active in the area of materials and chemistry R & D in support of GEN IV SCWR, this book presents for the first time a comprehensive reference on these topics, and in particular, how these data relate to the SCWR design itself. This book is an essential text for researchers in the areas of supercritical water-cooled reactor materials and chemistry, working in industry or academia. It will also give newcomers to the field a survey of all of the available literature and a clear understanding of how these studies relate to the design of the SCWR concept. The material presented is at a specialist's level in materials or corrosion science, or in water chemistry of power plants. Provides comprehensive coverage of the chemistry and materials of SCWRPresents the latest research and results condensed into one bookCovers the differences in use of SCW in nuclear reactors and fossil plants, and the resulting differences in materials requirements
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