Nonferrous Metal Products

    Boundary-Layer Flow of a Nanofluid past a Stretching Sheet under Uniform Heat and Mass Flux

    Evaluation of Plasma Transferred Arc Fe-Al Alloyed Coatings

    Microstructural Characterization of Layers Produced by Plasma Nitriding on Austenitic and Superaustenitic Stainless Steel Grades

    Effect of Chemical Modification of Al-Si Alloys on Thermal Diffusivity and Contact Heat Transfer at the Casting–Chill Interface

    5083 Aluminum Alloy Welded Joints: Measurements of Mechanical Properties by DIC

    Corrosion of M5 in PWRs: Quantification of Li, B, H and Nb in the Oxide Layers Formed Under Different Conditions

    Studies Regarding Corrosion Mechanisms in Zirconium Alloys

    Understanding Crack Formation at the Metal/Oxide Interface During Corrosion of Zircaloy-4 Using a Simple Mechanical Model

    Service Life Assessment of a Low-Slope 55 % Al–Zn Alloy-Coated Steel Standing Seam Roof System

    Effect of Additional Elements on Microstructure and Properties of CrN Coatings

    Influence of Structure on Brittleness of Boron Nitride Coatings Deposited on Cemented Fine-Grained Carbides

    Impact Wear Performance of Thin Hard Coatings on TiC Cermets

    Detailed Analysis of the Microstructure of the Metal/Oxide Interface Region in Zircaloy-2 after Autoclave Corrosion Testing

    Microstructural Studies of Heat Treated Zr-2.5Nb Alloy for Pressure Tube Applications

    Effect of Temperature and Pressure on Wear Properties of Ion Nitrided AISI 316 and 409 Stainless Steels

    Application of Numerical Methods to Simulate Direct Immersion Quenching Process

    Influence of Precorrosion on Fatigue Properties of Shot-Peened Aluminium 7075-T651

    Hydrogen Absorption Mechanism of Zirconium Alloys Based on Characterization of Oxide Layer

    Ultra Low Tin Quaternary Alloys PWR Performance—Impact of Tin Content on Corrosion Resistance, Irradiation Growth, and Mechanical Properties

    Effect of Aluminum Coating by Magnetron Sputtering on Corrosion Resistance of AZ31B Alloy

    Interdiffusion Phenomena of Zirconia-Nitride Layers on Coated AISI 310 Steel

    Modification of NiAl Intermetallic Coatings Processed by PTA with Chromium Carbides

    In Situ Scanning Electron Microscope Observation and Finite Element Method Analysis of Delayed Hydride Cracking Propagation in Zircaloy-2 Fuel Cladding Tubes

    CVD of Alternated MCD and NCD Films on Cemented Carbide Inserts

    Effect of Gas Pressure on Active Screen Plasma Nitriding Response

    ZIRLO® Irradiation Creep Stress Dependence in Compression and Tension

    Experimental Investigation of Irradiation Creep and Growth of Recrystallized Zircaloy-4 Guide Tubes Pre-Irradiated in PWR

    Study on the Role of Second Phase Particles in Hydrogen Uptake Behavior of Zirconium Alloys

    Damage Build-Up in Zirconium Alloys During Mechanical Processing: Application to Cold Pilgering

    Characterization of Oxygen Distribution in LOCA Situations

    Polycrystalline Modeling of the Effect of Texture and Dislocation Microstructure on Anisotropic Thermal Creep of Pressurized Zr-2.5Nb Tubes

    Evaluation of Cutting Edges Made of Nanocrystalline Cemented Carbides Sintered by the Pulse Plasma Method

    Effect of the Thermo-Mechanical Processing Characteristics on the Recrystallization of CuZn34 Brass

    Modeling and Simulation of the Heat and Mass Transfer Characteristics of Binary Mixtures for Boiling Flow Applications

    Improved Zr-2.5Nb Pressure Tubes for Reduced Diametral Strain in Advanced CANDU Reactors

    Radiation Damage of E635 Alloy Under High Dose Irradiation in the VVER-1000 and BOR-60 Reactors

    Hydrogen Solubility and Microstructural Changes in Zircaloy-4 Due to Neutron Irradiation

    Study of the Initial Stage and Anisotropic Growth of Oxide Layers Formed on Zircaloy-4

    Effect of Hydrides on Mechanical Properties and Failure Morphology of BWR Fuel Cladding at Very High Strain Rate

    Statistical Analysis of Hydride Reorientation Properties in Irradiated Zircaloy-2

    Multiscale Analysis of Viscoplastic Behavior of Recrystallized Zircaloy-4 at 400°C

    Hydride Platelet Reorientation in Zircaloy Studied with Synchrotron Radiation Diffraction

    A Review of Pb-Free High-Temperature Solders for Power-Semiconductor Devices: Bi-Base Composite Solder and Zn–Al Base Solder

    In Situ Studies of Variant Selection During the α-β-α Phase Transformation in Zr-2.5Nb

    RIA Failure of High Burnup Fuel Rod Irradiated in the Leibstadt Reactor: Out-of-Pile Mechanical Simulation and Comparison with Pulse Reactor Tests

    Impact of Irradiation Damage Recovery During Transportation on the Subsequent Room Temperature Tensile Behavior of Irradiated Zirconium Alloys

    Texture Evolution of Zircaloy-2 During Beta-Quenching: Effect of Process Variables

    Advanced Zirconium Alloy for PWR Application

    Shadow Corrosion-Induced Bow of Zircaloy-2 Channels

    Segregation in Vacuum Arc Remelted Zirconium Alloy Ingots

    Dynamic Recrystallization in Zirconium Alloys

    Explosion Cladding: An Enabling Technology for Zirconium in the Chemical Process Industry

    The Development of Zr-2.5Nb Pressure Tubes for CANDU Reactors

    REFLET Experiment in OSIRIS: Relaxation under Flux as a Method for Determining Creep Behavior of Zircaloy Assembly Components

    Photoelectrochemical Investigation of Radiation-Enhanced Shadow Corrosion Phenomenon

    Optimization of Zry-2 for High Burnups

    High Temperature Aqueous Corrosion and Deuterium Uptake of Coupons Prepared from the Front and Back Ends of Zr-2.5Nb Pressure Tubes

    The Evolution of Microstructure and Deformation Stability in Zr–Nb–(Sn,Fe) Alloys Under Neutron Irradiation

    Measurement and Modeling of Second Phase Precipitation Kinetics in Zirconium Niobium Alloys

    Simulation of Outside-in Cracking in Boiling Water Reactor Fuel Cladding Tubes under Power Ramp

    Performance of Zirconium Alloys in Light Water Reactors with a Review of Nodular Corrosion

    The Effect of Microstructure on Delayed Hydride Cracking Behavior of Zircaloy-4 Fuel Cladding—An International Atomic Energy Agency Coordinated Research Program

    Tensile Properties of Sn-10Sb-5Cu High Temperature Lead Free Solder

    Glass Formation and Mechanical Properties of Ti–Cu–Ni Alloys with High Ti Content

    Use of Fe–31Mn–7.5Al–1.3Si–0.9C Alloy for Fabrication of Resistive Elements

    Dilatometric Analysis to Study Aging of Aluminum Alloys

    Evolution of Quench Factor Analysis: A Review

    In PWR Comprehensive Study of High Burn-Up Corrosion and Growth Behavior of M5® and Recrystallized Low-Tin Zircaloy-4

    Dilatometric Analysis for Investigating Age Hardening in a Commercial Precious Metal Dental Alloy

    Water and Polymer Quenching of Aluminum Alloys: A Review of the Effect of Surface Condition, Water Temperature, and Polymer Quenchant Concentration on the Yield Strength of 7075-T6 Aluminum Plate

    Investigation of Irradiation Hardening and Embrittlement of Zr-2.5%Nb Alloy with High-Energy (e,γ)-Beams

    Characterization of Local Strain Distribution in Zircaloy-4 and M5® Alloys

    Evaluation of Hydride Reorientation Behavior and Mechanical Properties for High-Burnup Fuel-Cladding Tubes in Interim Dry Storage

    Toward a Better Understanding of Dimensional Changes in Zircaloy-4: What is the Impact Induced by Hydrides and Oxide Layer?

    Influence of Microstructure on the Mechanical Properties of Thixomolded® Magnesium Alloys

    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

    ZIRLOTM 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

    Evaluating Methods for Water Vapor Transmission of Moisture Vapor Suppression Coatings on Concrete

    The Monitoring of Crystallite Size By an X-Ray Method Applicable to the Processing and Synthesis of Micron-Sized Powders

    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 ZIRLOTM 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