SEDL / Topics / Nonferrous Metal Products / All JAI

• 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
• 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
• 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 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