Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors: Volume 2 (Hardcover, 2018)

Part 1. PWR Nickel SCC - SCC.- 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.- Applicability of Alloy 690/52/152 Crack Growth Testing Conditions to Plant Components.- SCC of Alloy 152/52 Welds Defects, Repairs and Dilution Zones in PWR Water.- NRC Perspectives on Primary Water Stress Corrosion Cracking of High-chromium, Nickel-based Alloys.- Stress Corrosion Cracking of 52/152 Weldments near Dissimilar Metal Weld Interfaces.- Composite Material Stress Corrosion Crack Arrest Testing in Hydrogen Deaerated Water.- Investigation of Hydrogen Behavior in Relation to the PWSCC Mechanism in Alloy TT690.- Part 2. PWR Nickel SCC - Initiation.- Crack Initiation of Alloy 600 in PWR Water.- SCC Initiation Behavior of Alloy 182 in PWR Primary Water.- Multiple Cracks Interactions in Stress Corrosion Cracking: In-situ Observation by Digital Image Correlation and Phase Field Modelling.- Stress Corrosion Cracking Initiation of Alloy 82 in Hydrogenated Steam.- Application of Ultra-high Pressure Cavitation Peening on Reactor Vessel Head Penetration, BMN and Primary Nozzles.- The Effect of Surface Condition on Primary Water Stress Corrosion Cracking Initiation of Alloy 600.- Microstructural Effects on SCC Initiation in Simulated PWR Primary Water for Cold-worked Alloy 600.- Part 3. PWR Nickel SCC - Aging Effects.- A Kinetic Study of Order-disorder Transition in Ni-Cr Based Alloys.- The Role of Stoichiometry on Ordering Phase Transformations in Ni-Cr Alloys for Nuclear Applications.- The Effect of Hardening via Long Range Order on the SCC and LTCP Susceptibility of a Nickel-30Chromium Binary Alloy.- PWSCC Initiation of Alloy 600: Effect of Long-term Thermal Aging and Triaxial Stress.- Stress Corrosion Cracking Behavior of Alloy 718 Subjected to Various Thermal Mechanical Treatments in Primary Water.- Time- and Fluence-to-fracture Studies of Alloy 718 in Reactor.- Development of Short-range Order and Intergranular Ccarbide Precipitation in Alloy 690 TT upon Thermal Ageing.- Part. 4. PWR Nickel SCC - Alloy 600 Mechanistic.- Diffusion Processes as a Possible Mechanism for Cr Depletion at SCC Crack Tip.- Role of Grain Boundary Cr 5 B 3 Precipitates on Intergranular Attack in Alloy 600.- Advanced Characterization of Oxidation Processes and Grain Boundary Migration in Ni Alloys Exposed to 480 °C Hydrogenated Steam.- Exploring Nanoscale Precursor Reactions in Alloy 600 in H2/N2-H2O Vapor Using In Situ Analytical Transmission Electron Microscopy.- Electrochemical and Microstructural Characterization of Alloy 600 in Low Pressure H 2 origin: initial; background-clip: initial;"-Steam.- 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.- A Mechanistic Study of the Effect of Temperature on Crack Propagation in Alloy 600 under PWR Primary Water Conditions.- Part 5. PWR Nickel SCC - Alloy 690 Mechanistic.- Grain Boundary Damage Evolution and SCC Initiation of Cold-worked Alloy 690 in Simulated PWR Primary Water.- Effect of Cold Work and Grain Boundary Carbides on PWSCC Susceptibility of Alloy 690.- Relationship among Dislocation Density, Local Strain Distribution, and PWSCC Susceptibility of Alloy 690.- Morphology Evolution of Grain Boundary Carbides Precipitated near Triple Junctions in Highly Twinned Alloy 690.- A Mechanistic Study on the Stress Corrosion Crack Propagation for Heavily Cold Worked TT Alloy 690 in Simulated PWR Primary Water.- Microstructural Study on the Stress Corrosion Cracking of Alloy 690 in Simulated Pressurized Water Reactor Primary Environment.- Part 6. Effect of Strain Rate and High Temperature Water on Deformation Structure of VVER Neutron Irradiated Core Internals Steel.- Radiation-Induced Precipitates in a Self-Ion Irradiated Cold-Worked 316 Austenitic Stainless Steel Used for PWR Baffle-Bolts.- In Situ and Ex Situ Observations