ASTM International Technical Committee B10 Publications

Technical Committees / Committee B10 / Committee Publications

Journal of ASTM International

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
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
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
In Situ Scanning Electron Microscope Observation and Finite Element Method Analysis of Delayed Hydride Cracking Propagation in Zircaloy-2 Fuel Cladding Tubes
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
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
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
Glass Formation and Mechanical Properties of Ti–Cu–Ni Alloys with High Ti Content
In PWR Comprehensive Study of High Burn-Up Corrosion and Growth Behavior of M5^® and Recrystallized Low-Tin Zircaloy-4
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 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
Studies of Corrosion of Cladding Materials in Simulated BWR Environment using Impedance Measurements
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
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
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
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