Digital Library / Past Symposia for Committee B10 / Zirconium in the Nuclear Industry: 15th International Symposium

Sponsored by ASTM committee B10 on Reactive and Refractory Metals and Alloys

June 24 2007 - June 28 2007

• 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 Effect of Hydrogen on the Transition Behavior of the Corrosion Rate of Zirconium 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
• 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