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Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors

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Table of Contents

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    Book Overview
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    Chapter 1 Scoring Process for Evaluating Laboratory PWSCC Crack Growth Rate Data of Thick-Wall Alloy 690 Wrought Material and Alloy 52, 152, and Variant Weld Material
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    Chapter 2 Applicability of Alloy 690/52/152 Crack Growth Testing Conditions to Plant Components
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    Chapter 3 SCC of Alloy 152/52 Welds Defects, Repairs and Dilution Zones in PWR Water
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    Chapter 4 NRC Perspectives on Primary Water Stress Corrosion Cracking of High-Chromium, Nickel-Based Alloys
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    Chapter 5 Stress Corrosion Cracking of Alloy 52/152 Weldments Near Dissimilar Metal Weld Interfaces
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    Chapter 6 Stress Corrosion Crack Growth Rate Testing of Composite Material Specimens
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    Chapter 7 Investigation of Hydrogen Behavior in Relation to the PWSCC Mechanism in Alloy TT690
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    Chapter 8 Crack Initiation of Alloy 600 in PWR Water
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    Chapter 9 SCC Initiation Behavior of Alloy 182 in PWR Primary Water
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    Chapter 10 Multiple Cracks Interactions in Stress Corrosion Cracking: In Situ Observation by Digital Image Correlation and Phase Field Modeling
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    Chapter 11 Stress Corrosion Cracking Initiation of Alloy 82 in Hydrogenated Steam
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    Chapter 12 Application of Ultra-High Pressure Cavitation Peening on Reactor Vessel Head Penetration, BMN and Primary Nozzles
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    Chapter 13 The Effect of Surface Condition on Primary Water Stress Corrosion Cracking Initiation of Alloy 600
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    Chapter 14 Microstructural Effects on SCC Initiation in PWR Primary Water for Cold-Worked Alloy 600
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    Chapter 15 A Kinetic Study of Order-Disorder Transition in Ni–Cr Based Alloys
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    Chapter 16 The Role of Stoichiometry on Ordering Phase Transformations in Ni–Cr Alloys for Nuclear Applications
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    Chapter 17 The Effect of Hardening via Long Range Order on the SCC and LTCP Susceptibility of a Nickel-30Chromium Binary Alloy
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    Chapter 18 PWSCC Initiation of Alloy 600: Effect of Long-Term Thermal Aging and Triaxial Stress
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    Chapter 19 Stress Corrosion Cracking Behavior of Alloy 718 Subjected to Various Thermal Mechanical Treatments in Primary Water
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    Chapter 20 Time- and Fluence-to-fracture Studies of Alloy 718 in Reactor
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    Chapter 21 Development of Short-Range Order and Intergranular Carbide Precipitation in Alloy 690 TT upon Thermal Ageing
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    Chapter 22 Diffusion Processes as Possible Mechanisms for Cr Depletion at SCC Crack Tip
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    Chapter 23 Role of Grain Boundary Cr 5 B 3 Precipitates on Intergranular Attack in Alloy 600
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    Chapter 24 Advanced Characterization of Oxidation Processes and Grain Boundary Migration in Ni Alloys Exposed to 480 °C Hydrogenated Steam
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    Chapter 25 Exploring Nanoscale Precursor Reactions in Alloy 600 in H 2 /N 2 –H 2 O Vapor Using In Situ Analytical Transmission Electron Microscopy
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    Chapter 26 Electrochemical and Microstructural Characterization of Alloy 600 in Low Pressure H 2 -Steam
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    Chapter 27 Effect of Dissolved Hydrogen on the Crack Growth Rate and Oxide Film Formation at the Crack Tip of Alloy 600 Exposed to Simulated PWR Primary Water
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    Chapter 28 A Mechanistic Study of the Effect of Temperature on Crack Propagation in Alloy 600 Under PWR Primary Water Conditions
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    Chapter 29 Grain Boundary Damage Evolution and SCC Initiation of Cold-Worked Alloy 690 in Simulated PWR Primary Water
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    Chapter 30 PWSCC Susceptibility of Alloy 690, 52 and 152
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    Chapter 31 Relationship Among Dislocation Density, Local Strain Distribution, and PWSCC Susceptibility of Alloy 690
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    Chapter 32 Morphology Evolution of Grain Boundary Carbides Precipitated Near Triple Junctions in Highly Twinned Alloy 690
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    Chapter 33 A Mechanistic Study of Stress Corrosion Crack Propagation in Heavily Cold Worked TT Alloy 690 Exposed to Simulated PWR Primary Water
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    Chapter 34 Microstructural Study on the Stress Corrosion Cracking of Alloy 690 in Simulated Pressurized Water Reactor Primary Environment
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    Chapter 35 Effect of Strain Rate and High Temperature Water on Deformation Structure of VVER Neutron Irradiated Core Internals Steel
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    Chapter 36 Radiation-Induced Precipitates in a Self-ion Irradiated Cold-Worked 316 Austenitic Stainless Steel Used for PWR Baffle-Bolts
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    Chapter 37 In Situ and Ex Situ Observations of the Influence of Twin Boundaries on Heavy Ion Irradiation Damage Effects in 316L Austenitic Stainless Steels
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    Chapter 38 In Situ Microtensile Testing for Ion Beam Irradiated Materials
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    Chapter 39 Development of High Irradiation Resistant and Corrosion Resistant Oxide Dispersion Strengthened Austenitic Stainless Steels
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    Chapter 40 Spherical Nanoindentation Stress-Strain Analysis of Ion-Irradiated Tungsten
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    Chapter 41 Formation of He Bubbles by Repair-Welding in Neutron-Irradiated Stainless Steels Containing Surface Cold-Worked Layer
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    Chapter 42 Predictions and Measurements of Helium and Hydrogen in PWR Structural Components Following Neutron Irradiation and Subsequent Charged Particle Bombardment
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    Chapter 43 Emulating Neutron-Induced Void Swelling in Stainless Steels Using Ion Irradiation
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    Chapter 44 Carbon Contamination, Its Consequences and Its Mitigation in Ion-Simulation of Neutron-Induced Swelling of Structural Metals
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    Chapter 45 Void Swelling Screening Criteria for Stainless Steels in PWR Systems
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    Chapter 46 Theoretical Study of Swelling of Structural Materials in Light Water Reactors at High Fluencies
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    Chapter 47 High Resolution Transmission Electron Microscopy of Irradiation Damage in Inconel X-750
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    Chapter 48 In Situ SEM Push-to-Pull Micro-tensile Testing of Ex-service Inconel X-750
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    Chapter 49 Microstructural Characterization of Proton-Irradiated 316 Stainless Steels by Transmission Electron Microscopy and Atom Probe Tomography
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    Chapter 50 Microstructural Effects on Stress Corrosion Initiation in Austenitic Stainless Steel in PWR Environments
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    Chapter 51 Oxidation and SCC Initiation Studies of Type 304L SS in PWR Primary Water
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    Chapter 52 SCC Initiation in the Machined Austenitic Stainless Steel 316L in Simulated PWR Primary Water
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    Chapter 53 High-Resolution Characterisation of Austenitic Stainless Steel in PWR Environments: Effect of Strain and Surface Finish on Crack Initiation and Propagation
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    Chapter 54 SCC of Austenitic Stainless Steels Under Off-Normal Water Chemistry and Surface Conditions
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    Chapter 55 SCC of Austenitic Stainless Steels Under Off-Normal Water Chemistry and Surface Conditions
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    Chapter 56 The Effect of Microchemistry on the Crack Response of Lightly Cold Worked Dual Certified Type 304/304L Stainless Steel After Sensitizing Heat Treatment
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    Chapter 57 The Effect of Load Ratio on the Fatigue Crack Growth Rate of Type 304 Stainless Steels in Air and High Temperature Deaerated Water at 482 °F
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    Chapter 58 Electrical Potential Drop Observations of Fatigue Crack Closure
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    Chapter 59 The Effect of Environment and Material Chemistry on Single-Effects Creep Testing of Austenitic Stainless Steels
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    Chapter 60 Corrosion Fatigue Behavior of Austenitic Stainless Steel in a Pure D 2 O Environment
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    Chapter 61 Mechanistic Understanding of Environmentally Assisted Fatigue Crack Growth of Austenitic Stainless Steels in PWR Environments
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    Chapter 62 Study on Hold-Time Effects in Environmental Fatigue Lifetime of Low-Alloy Steel and Austenitic Stainless Steel in Air and Under Simulated PWR Primary Water Conditions
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    Chapter 63 Evaluation of Additively Manufactured Materials for Nuclear Plant Components
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    Chapter 64 Hot Cell Tensile Testing of Neutron Irradiated Additively Manufactured Type 316L Stainless Steel
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    Chapter 65 Computational and Experimental Studies on Novel Materials for Fission Gas Capture
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    Chapter 66 Hydrogen Assisted Cracking Studies of a 12% Chromium Martensitic Stainless Steel—Influence of Hardness, Stress and Environment
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    Chapter 67 Investigation of Flow Accelerated Corrosion Models to Predict the Corrosion Behavior of Coated Carbon Steels in Secondary Piping Systems
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    Chapter 68 Effect of High-Temperature Water Environment on the Fracture Behaviour of Low-Alloy RPV Steels
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    Chapter 69 Corrosion Fatigue Testing of Low Alloy Steel in Water Environment with Low Levels of Oxygen and Varied Load Dwell Times
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    Chapter 70 Feasibility Study of the Internal Zr/ZrO 2 Reference Electrodes in Supercritical Water Environments
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    Chapter 71 Investigation of Pitting Corrosion in Sensitized Modified High-Nitrogen 316LN Steel After Neutron Irradiation
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    Chapter 72 Quantifying Erosion-Corrosion Impacts on Light Water Reactor Piping
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    Chapter 73 Effect of Molybdate Anion Addition on Repassivation of Corroding Crevice in Austenitic Stainless Steel
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    Chapter 74 Effect of pH on Hydrogen Pick-Up and Corrosion in Zircaloy-4
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    Chapter 75 Oxidation Kinetics of Austenitic Stainless Steels as SCWR Fuel Cladding Candidate Materials in Supercritical Water
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    Chapter 76 A Recent Look at CANDU Feeder Cracking: High Resolution Transmission Electron Microscopy and Electron Energy Loss Near Edge Structure (ELNES)
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    Chapter 77 Simultaneous Thermal and Gamma Radiation Aging of Electrical Cable Polymers
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    Chapter 78 Principal Component Analysis (PCA) as a Statistical Tool for Identifying Key Indicators of Nuclear Power Plant Cable Insulation Degradation
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    Chapter 79 How Can Material Characterization Support Cable Aging Management?
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    Chapter 80 Aqueous Degradation in Harvested Medium Voltage Cables in Nuclear Power Plants
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    Chapter 81 Frequency Domain Reflectometry Modeling and Measurement for Nondestructive Evaluation of Nuclear Power Plant Cables
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    Chapter 82 Aging Mechanisms and Nondestructive Aging Indicator of Filled Cross-Linked Polyethylene (XLPE) Exposed to Simultaneous Thermal and Gamma Radiation
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    Chapter 83 Successful Detection of Insulation Degradation in Cables by Frequency Domain Reflectometry
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    Chapter 84 Capacitive Nondestructive Evaluation of Aged Cross-Linked Polyethylene (XLPE) Cable Insulation Material
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    Chapter 85 Tracking of Nuclear Cable Insulation Polymer Structural Changes Using the Gel Fraction and Uptake Factor Method
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    Chapter 86 Degradation of Silicone Rubber Analyzed by Instrumental Analyses and Dielectric Spectroscopy
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    Chapter 87 Automated Detection of Alkali-Silica Reaction in Concrete Using Linear Array Ultrasound Data
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    Chapter 88 Coupled Physics Simulation of Expansive Reactions in Concrete with the Grizzly Code
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    Chapter 89 Overview of EPRI Long Term Operations Work on Nuclear Power Plant Concrete Structures
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    Chapter 90 The Effects of Neutron Irradiation on the Mechanical Properties of Mineral Analogues of Concrete Aggregates
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    Chapter 91 Accident Tolerant FeCrAl Fuel Cladding: Current Status Towards Commercialization
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    Chapter 92 Interdiffusion Behavior of FeCrAl with U 3 Si 2
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    Chapter 93 Mechanical Behavior of FeCrAl and Other Alloys Following Exposure to LOCA Conditions Plus Quenching
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    Chapter 94 Mechanical Behavior and Structure of Advanced Fe-Cr-Al Alloy Weldments
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    Chapter 95 Investigating Potential Accident Tolerant Fuel Cladding Materials and Coatings
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    Chapter 96 Steam Oxidation Behavior of FeCrAl Cladding
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    Chapter 97 In-Situ Proton Irradiation-Corrosion Study of ATF Candidate Alloys in Simulated PWR Primary Water
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    Chapter 98 Hydrothermal Corrosion of SiC Materials for Accident Tolerant Fuel Cladding with and Without Mitigation Coatings
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    Chapter 99 Characterization of the Hydrothermal Corrosion Behavior of Ceramics for Accident Tolerant Fuel Cladding
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    Chapter 100 Corrosion of Multilayer Ceramic-Coated ZIRLO Exposed to High Temperature Water
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    Chapter 101 Calibration of the Local IGSCC Engineering Model for Alloy 600
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    Chapter 102 Prediction of IGSCC as a Finite Element Modeling Post-analysis
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    Chapter 103 Monte Carlo Simulation Based on SCC Test Results in Hydrogenated Steam Environment for Alloy 600
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    Chapter 104 Protection of the Steel Used for Dry Cask Storage System from Atmospheric Corrosion by Tio 2 Coating
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    Chapter 105 Predictive Modeling of Baffle-Former Bolt Failures in Pressurized Water Reactors
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    Chapter 106 Technical Basis and SCC Growth Rate Data to Develop an SCC Disposition Curve for Alloy 82 in BWR Environments
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    Chapter 107 SCC and Fracture Toughness of XM-19
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    Chapter 108 On the Effect of Preoxidation of Nickel Alloy X-750
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    Chapter 109 Microstructures of Oxide Films Formed in Alloy 182 BWR Core Shroud Support Leg Cracks
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    Chapter 110 Effect of Chloride Transients on Crack Growth Rates in Low Alloy Steels in BWR Environments
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    Chapter 111 Electrochemical Behavior of Platinum Treated Type 304 Stainless Steels in Simulated BWR Environments Under Startup Conditions
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    Chapter 112 Investigations of the Dual Benefits of Zinc Injection on Cobalt-60 Uptake and Oxide Film Formation Under Boiling Water Reactor Conditions
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    Chapter 113 SCC Mitigation in Boiling Water Reactors: Platinum Deposition and Durability on Structural Materials
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    Chapter 114 Confirmation of On-Line NobleChem™ (OLNC) Mitigation Effectiveness in Operating Boiling Water Reactors (BWRs)
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    Chapter 115 Development of the Fundamental Multiphysics Analysis Model for Crevice Corrosion Using a Finite Element Method
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    Chapter 116 In Situ Electrochemical Study on Crevice Environment of Stainless Steel in High Temperature Water
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    Chapter 117 Corrosion Fatigue Crack Initiation in Zr-2.5Nb
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    Chapter 118 Cluster Dynamics Model for the Hydride Precipitation Kinetics in Zirconium Cladding
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    Chapter 119 Modeling Corrosion Kinetics of Zirconium Alloys in Loss-of-Coolant Accident (LOCA)
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    Chapter 120 Progressing Zirconium-Alloy Corrosion Models Using Synchrotron XANES
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    Chapter 121 Advanced Characterization of Hydrides in Zirconium Alloys
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    Chapter 122 Influence of Alloying Elements and Effect of Stress on Anisotropic Hydrogen Diffusion in Zr-Based Alloys Predicted by Accelerated Kinetic Monte Carlo Simulations
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    Chapter 123 Influence of δ-Ferrite Content on Thermal Aging Induced Mechanical Property Degradation in Cast Stainless Steels
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    Chapter 124 Microstructure and Deformation Behavior of Thermally Aged Cast Austenitic Stainless Steels
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    Chapter 125 Microstructural Evolution of Cast Austenitic Stainless Steels Under Accelerated Thermal Aging
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    Chapter 126 Electrochemical Characteristics of Delta Ferrite in Thermally Aged Austenitic Stainless Steel Weld
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    Chapter 127 Effect of Long-Term Thermal Aging on SCC Initiation Susceptibility in Low Carbon Austenitic Stainless Steels
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    Chapter 128 Crack Growth Rate and Fracture Toughness of CF3 Cast Stainless Steels at ~3 DPA
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    Chapter 129 Effects of Thermal Aging and Low Dose Neutron Irradiation on the Ferrite Phase in a 308L Weld
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    Chapter 130 Microstructural Evolution of Welded Stainless Steels on Integrated Effect of Thermal Aging and Low Flux Irradiation
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    Chapter 131 The Use of Tapered Specimens to Evaluate the SCC Initiation Susceptibility in Alloy 182 in BWR and PWR Environments
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    Chapter 132 Effect of Thermal Aging on Fracture Mechanical Properties and Crack Propagation Behavior of Alloy 52 Narrow-Gap Dissimilar Metal Weld
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    Chapter 133 Distribution and Characteristics of Oxide Films Formed on Stainless Steel Cladding on Low Alloy Steel in Simulated PWR Primary Water Environments
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    Chapter 134 Microstructural Characterization of Alloy 52 Narrow-Gap Dissimilar Metal Weld After Aging
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    Chapter 135 A Statistical Analysis on Modeling Uncertainty Through Crack Initiation Tests
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    Chapter 136 Laboratory Analysis of a Leaking Letdown Cooler from Oconee Unit 3
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    Chapter 137 Root Cause Analysis of Cracking in Alloy 182 BWR Core Shroud Support Leg Cracks
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    Chapter 138 Microbially Induced Corrosion in Firefighting Systems—Experience and Remedies
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    Chapter 139 Managing the Ageing Degradation of Concealed Safety Relevant Cooling Water Piping in European S/KWU LWRs
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    Chapter 140 Identification of PWR Stainless Steel Piping Safety Significant Locations Susceptible to Stress Corrosion Cracking
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    Chapter 141 On the Use of Density-Based Algorithms for the Analysis of Solute Clustering in Atom Probe Tomography Data
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    Chapter 142 Comparative Study on Short Time Oxidation of Un-Irradiated and Protons Pre-Irradiated 316L Stainless Steel in Simulated PWR Water
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    Chapter 143 Hydrogen Trapping by Irradiation-Induced Defects in 316L Stainless Steel
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    Chapter 144 Grain Boundary Oxidation of Neutron Irradiated Stainless Steels in Simulated PWR Water
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    Chapter 145 Irradiation Assisted Stress Corrosion Cracking (IASCC) of Nickel-Base Alloys in Light Water Reactors Environments—Part I: Microstructure Characterization
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    Chapter 146 Irradiation Assisted Stress Corrosion Cracking (IASCC) of Nickel-Base Alloys in Light Water Reactors Environments Part II: Stress Corrosion Cracking
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    Chapter 147 Solute Clustering in As-irradiated and Post-irradiation-Annealed 304 Stainless Steel
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    Chapter 148 Irradiation-Assisted Stress Corrosion Cracking Initiation Screening Criteria for Stainless Steels in PWR Systems
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    Chapter 149 Novel Technique for Quantitative Measurement of Localized Stresses Near Dislocation Channel—Grain Boundary Interaction Sites in Irradiated Stainless Steel
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    Chapter 150 IASCC Susceptibility of 304L Stainless Steel Irradiated in a BWR and Subjected to Post Irradiation Annealing
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    Chapter 151 Irradiation Assisted Stress Corrosion Cracking Susceptibility of Alloy X-750 Exposed to BWR Environments
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    Chapter 152 Evaluation of Crack Growth Rates and Microstructures Near the Crack Tip of Neutron-Irradiated Austenitic Stainless Steels in Simulated BWR Environment
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    Chapter 153 Effect of Specimen Size on the Crack Growth Rate Behavior of Irradiated Type 304 Stainless Steel
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    Chapter 154 Plastic Deformation Processes Accompanying Stress Corrosion Crack Propagation in Irradiated Austenitic Steels
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    Chapter 155 Effect of Grain Orientation on Irradiation Assisted Corrosion of 316L Stainless Steel in Simulated PWR Primary Water
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    Chapter 156 Finite Element Modelling to Investigate the Mechanisms of CRUD Deposition in PWR
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    Chapter 157 Properties of Oxide Films on Ni–Cr– x Fe Alloys in a Simulated PWR Water Environment
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    Chapter 158 Effect of Applied Potential and Inhibitors on PbSCC of Alloy 690TT
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    Chapter 159 Corrosion of SG Tube Alloys in Typical Secondary Side Local Chemistries Derived from Operating Experience
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    Chapter 160 Investigation on the Effect of Lead (Pb) on the Degradation Behavior of Passive Films on Alloy 800
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    Chapter 161 Influence of Alloying on α-αʹ Phase Separation in Duplex Stainless Steels
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    Chapter 162 Stress Corrosion Cracking of Alloy 800 in Secondary Side Crevice Environment
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    Chapter 163 Using Modern Microscopy to “Fingerprint” Secondary Side SCC in Ni–Fe Alloys
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Title
Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
Published by
Springer International Publishing, February 2019
DOI 10.1007/978-3-030-04639-2
ISBNs
978-3-03-004638-5, 978-3-03-004639-2
Editors

Jackson, John H., Paraventi, Denise, Wright, Michael

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