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• Influence of Structure Changes in E110 Alloy Claddings on Ductility Loss Under LOCA Conditions
• Contribution of Thermodynamic Calculations to Metallurgical Studies of Multi-Component Zirconium Based Alloys
• Tearing Crack Growth and Fracture Micro-Mechanisms Under Micro Segregation in Zr-2.5%Nb Pressure Tube Material
• Investigation of Structural and Chemical Uniformity of Zr2.5% Nb and E635 Alloy by Radioactive Indicators
• ZIRLO^TM Cladding Improvement
• In Situ EIS Measurements of Irradiated Zircaloy-4 Post-Transition Corrosion Kinetic Behavior
• Role of Twinning and Slip in Deformation of a Zr-2.5Nb Tube
• Intergranular and Interphase Constraints in Zirconium Alloys
• In-Reactor Deformation of Zirconium Alloy Components
• Hydrogen Content, Preoxidation, and Cooling Scenario Effects on Post-Quench Microstructure and Mechanical Properties of Zircaloy-4 and M5^® Alloys in LOCA Conditions
• CASTA DIVA^®: Experiments and Modeling of Oxide-Induced Deformation in Nuclear Components
• Corrosion and Oxide Properties of HANA Alloys
• Experimental and Analytical Investigation of the Mechanical Behavior of High-Burnup Zircaloy-4 Fuel Cladding
• A New Model to Predict the Oxidation Kinetics of Zirconium Alloys in a Pressurized Water Reactor
• Irradiation-Induced Growth and Microstructure of Recrystallized, Cold Worked and Quenched Zircaloy-2, NSF, and E635 Alloys
• Investigations of the Microstructure and Mechanical Properties of Prior-β Structure as a Function of the Oxygen Content in Two Zirconium Alloys
• The Effect of Hydrogen on the Transition Behavior of the Corrosion Rate of Zirconium Alloys
• Experimental and Modeling Approach of Irradiation Defects Recovery in Zirconium Alloys: Impact of an Applied Stress
• Structure-Phase State, Corrosion and Irradiation Properties of Zr-Nb-Fe-Sn System Alloys
• Characterization of Zirconium Hydrides and Phase Field Approach to a Mesoscopic-Scale Modeling of Their Precipitation
• Microstructural Characterization of Oxides Formed on Model Zr Alloys Using Synchrotron Radiation
• Measurement of Rates of Delayed Hydride Cracking (DHC) in Zr-2.5Nb Alloys—An IAEA Coordinated Research Project
• Behavior and Mechanisms of Irradiation—Thermal Creep of Cladding Tubes Made of Zirconium Alloys
• Cladding Tube Deformation Test for Stress Reorientation of Hydrides
• Effect of Water Chemistry and Composition on Microstructural Evolution of Oxide on Zr Alloys
• Effects of Pt Surface Coverage on Oxidation of Zr and Other Materials
• Round-Robin Testing of Fracture Toughness Characteristics of Thin-Walled Tubing
• Effect of Irradiation Damage on the Deformation Properties of Zr-2.5Nb Pressure Tubes
• Deformation Anisotropy of Annealed Zircaloy-2 as a Function of Fast Neutron Fluence
• Microstructure Evolution in Zr Alloys during Irradiation: Dose, Dose Rate, and Impurity Dependence
• Fracture Toughness of Hydrided Zircaloy-4 Sheet Under Through-Thickness Crack Growth Conditions
• In-Pile Criteria for the Initiation of Massive Hydriding of Zr in Steam-Hydrogen Environment
• Determination and Interpretation of Texture Evolution during Deformation of a Zirconium Alloy
• Chemistry of Waterside Oxide Layers on Pressure Tubes
• A Study of the Structure and Chemistry in Zircaloy-2 and the Resulting Oxide After High Temperature Corrosion
• Mechanical Properties of Zr-2.5Nb Pressure Tubes Made from Electrolytic Powder
• Manufacturing Variability, Microstructure, and Deformation of Zr-2.5Nb Pressure Tubes
• Effect of Local Hydride Accumulations on Zircaloy Cladding Mechanical Properties
• Quality Assurance Program for Soldering Copper Roofs
• Studies of Corrosion of Cladding Materials in Simulated BWR Environment using Impedance Measurements
• Impact of Small Chemistry Variations in Plate and Weld Filler Metal on the Corrosion Performance of Ni-Cr-Mo Alloys²
• The Monitoring of Crystallite Size By an X-Ray Method Applicable to the Processing and Synthesis of Micron-Sized Powders
• Evaluating Methods for Water Vapor Transmission of Moisture Vapor Suppression Coatings on Concrete
• The Role of Applied Potential on Environment-Assisted Cracking of Zirconium Alloys
• Modeling of the Simultaneous Evolution of Vacancy and Interstitial Dislocation Loops in hcp Metals Under Irradiation
• Phase Composition, Structure, and Plastic Deformation Localization in Zr1%Nb alloys
• Effect of Alloying Elements and Impurities on in-BWR Corrosion of Zirconium Alloys
• Comparison of the High Burn-Up Corrosion on M5 and Low Tin Zircaloy-4
• Thermal Creep of Irradiated Zircaloy Cladding
• The Effect of Duplex Cladding Outer Component Tin Content on Corrosion, Hydrogen Pick-up, and Hydride Distribution at Very High Burnup
• Effect of Irradiation on the Fracture Properties of Zr-2.5Nb Pressure Tubes at the End of Design Life
• The Effect of Liner Component Iron Content on Cladding Corrosion, Hydriding, and PCI Resistance
• Destruction of Crystallographic Texture in Zirconium Alloy Tubes
• Plastic Deformation of Irradiated Zirconium Alloys: TEM Investigations and Micro-Mechanical Modeling
• Influence of Structure—Phase State of Nb Containing Zr Alloys on Irradiation-Induced Growth
• Delayed Hydrogen Cracking Velocity and J-Integral Measurements on Irradiated BWR Cladding
• Fretting-Wear Behavior of Zircaloy-4, OPTIN™, and ZIRLO™ Fuel Rods and Grid Supports Under Various Autoclave and Hydraulic Loop Endurance Test Conditions
• Microstructural Stability of M5™ Alloy Irradiated up to High Neutron Fluences
• Temperature and Strain Rate Effects on Zr-1%Nb Alloy Deformation
• Damage Dependence of Irradiation Deformation of Zr-2.5Nb Pressure Tubes
• Characterization and Analytical Application of the Ion-Association Complex of Nickel with Alizarin Yellow R and Eosin
• The Effect of Beta-Quenching in Final Dimension on the Irradiation Growth of Tubes and Channels
• Improved ZIRLO^TM Cladding Performance through Chemistry and Process Modifications
• Shadow Corrosion Mechanism of Zircaloy
• TEM Examinations of the Metal-Oxide Interface of Zirconium Based Alloys Irradiated in a Pressurized Water Reactor
• Failure of Hydrided Zircaloy-4 Under Equal-Biaxial and Plane-Strain Tensile Deformation
• Mechanical Properties of Zircaloy-4 PWR Fuel Cladding with Burnup 54-64MWd/kgU and Implications for RIA Behavior
• Wear Behavior of Niobium Boride Coatings
• On Secondary β-Nb Phase Precipitation within Primary α-Zr Phase in Zr-Nb Alloys During Tensile Deformation
• Study of Nb and Fe Precipitation in α-Phase Temperature Range (400 to 550°C) in Zr-Nb-(Fe-Sn) Alloys
• Predicting Oxidation and Deuterium Ingress for Zr-2.5Nb CANDU Pressure Tubes
• In-Core Tests of Effects of BWR Water Chemistry Impurities on Zircaloy Corrosion
• Microstructure and Growth Mechanism of Oxide Layers Formed on Zr Alloys Studied with Micro-Beam Synchrotron Radiation
• Ductility of Zircaloy-4 Fuel Cladding and Guide Tubes at High Fluences
• Microstructure and Phase Control in Zr-Fe-Cr-Ni Alloys: Thermodynamic and Kinetic Aspects
• Inhibitors for Reducing Hydrogen Ingress During Corrosion of Zirconium Alloys
• Overload Fracture of Flaw Tip Hydrides in Zr-2.5Nb Pressure Tubes
• In-Situ Studies of the Oxide Film Properties on BWR Fuel Cladding Materials
• Review of Deformation Mechanisms, Texture, and Mechanical Anisotropy in Zirconium and Zirconium Base Alloys
• Simulation of Cold Pilgering Process by a Generalized Plane Strain FEM
• Use of the Irradiation-Thermal Creep Model of Zr-1% Nb Alloy Cladding Tubes to Describe Dimensional Changes of VVER Fuel Rods
• Influence of Long Service Exposures on the Thermal-Mechanical Behavior of Zy-4 and M5™ Alloys in LOCA Conditions
• ZIRLO™ — An Alloy Development Success
• Ultrathin Films to Modify Mechanical and Tribological Behavior of MEMS Components
• The Correlation Between Microstructures and in-BWR Corrosion Behavior of Highly Irradiated Zr-based Alloys
• Role of Iron for Hydrogen Absorption Mechanism in Zirconium Alloys
• Identification of Crystalline Behavior on Macroscopic Response and Local Strain Field Analysis: Application to Alpha Zirconium Alloys
• Effect of Fabrication Variables on Irradiation Response of Crack Growth Resistance of Zr-2.5Nb