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    Zirconium in the Nuclear Industry: 15th International Symposium

    Kammenzind Bruce, Limbäck Magnus
    Published: 2009

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    The latest in this popular series provides 44 peer-reviewed papers on the latest international research covering all aspects of zirconium alloy properties and performance relevant to the nuclear industry.

    Topics address:

    • All aspects of the fuel cycle

    • Basic metallurgy

    • Spent fuel

    • Corrosion

    • Mechanical properties

    • Deformations mechanisms

    • Failure mechanisms

    • LOCA and Transients.

    These papers provide examples of studies where experimental techniques are combined with analytical tools and calculations; reflect a stronger trend towards efforts that enable fundamental in-reactor measurements, which are essential for further development of experimental techniques as well as for the possibility to enhance the development of improved alloys; and examine an increasing number of alternative alloys being developed and verified.

    Table of Contents

    In-Reactor Deformation of Zirconium Alloy Components

    Microstructure Evolution in Zr Alloys during Irradiation: Dose, Dose Rate, and Impurity Dependence

    Characterization of Zirconium Hydrides and Phase Field Approach to a Mesoscopic-Scale Modeling of Their Precipitation

    Influence of Structure Changes in E110 Alloy Claddings on Ductility Loss under LOCA Conditions

    Investigations of the Microstructure and Mechanical Properties of Prior-β Structure as a Function of the Oxygen Content in Two Zirconium Alloys

    Hydrogen Content, Preoxidation, and Cooling Scenario Effects on Post-Quench Microstructure and Mechanical Properties of Zircaloy-4 and M5® Alloys in LOCA Conditions

    Experimental and Analytical Investigation of the Mechanical Behavior of High-Burnup Zircaloy-4 Fuel Cladding

    Effect of Local Hydride Accumulations on Zircaloy Cladding Mechanical Properties

    Fracture Toughness of Hydrided Zircaloy-4 Sheet under through-Thickness Crack Growth Conditions

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

    In-Pile Criteria for the Initiation of Massive Hydriding of Zr in Steam-Hydrogen Environment

    Round-Robin Testing of Fracture Toughness Characteristics of Thin-Walled Tubing

    Role of Twinning and Slip in Deformation of a Zr-2.5Nb Tube

    Measurement of Rates of Delayed Hydride Cracking (DHC) in Zr-2.5Nb Alloys—An IAEA Coordinated Research Project

    A Study of the Structure and Chemistry in Zircaloy-2 and the Resulting Oxide After High Temperature Corrosion

    Effects of Pt Surface Coverage on Oxidation of Zr and Other Materials

    Studies of Corrosion of Cladding Materials in Simulated BWR Environment using Impedance Measurements

    In Situ EIS Measurements of Irradiated Zircaloy-4 Post-Transition Corrosion Kinetic Behavior

    Effect of Water Chemistry and Composition on Microstructural Evolution of Oxide on Zr Alloys

    The Effect of Hydrogen on the Transition Behavior of the Corrosion Rate of Zirconium Alloys

    A New Model to Predict the Oxidation Kinetics of Zirconium Alloys in a Pressurized Water Reactor

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

    ZIRLO™ Cladding Improvement

    Corrosion and Oxide Properties of HANA Alloys

    Microstructural Characterization of Oxides Formed on Model Zr Alloys Using Synchrotron Radiation

    Chemistry of Waterside Oxide Layers on Pressure Tubes

    Manufacturing Variability, Microstructure, and Deformation of Zr-2.5Nb Pressure Tubes

    Effect of Irradiation Damage on the Deformation Properties of Zr-2.5Nb Pressure Tubes

    Determination and Interpretation of Texture Evolution during Deformation of a Zirconium Alloy

    Irradiation-Induced Growth and Microstructure of Recrystallized, Cold Worked and Quenched Zircaloy-2, NSF, and E635 Alloys

    Deformation Anisotropy of Annealed Zircaloy-2 as a Function of Fast Neutron Fluence

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

    CASTA DIVA®: Experiments and Modeling of Oxide-Induced Deformation in Nuclear Components

    Cladding Tube Deformation Test for Stress Reorientation of Hydrides

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

    Experimental and Modeling Approach of Irradiation Defects Recovery in Zirconium Alloys: Impact of an Applied Stress

    Mechanical Properties of Zr-2.5Nb Pressure Tubes Made from Electrolytic Powder

    Structure-Phase State, Corrosion and Irradiation Properties of Zr-Nb-Fe-Sn System Alloys

    Investigation of Structural and Chemical Uniformity of Zr2.5% Nb and E635 Alloy by Radioactive Indicators

    Contribution of Thermodynamic Calculations to Metallurgical Studies of Multi-Component Zirconium Based Alloys

    Intergranular and Interphase Constraints in Zirconium Alloys

    Tearing Crack Growth and Fracture Micro-Mechanisms Under Micro Segregation in Zr-2.5%Nb Pressure Tube Material

    Committee: B10

    DOI: 10.1520/STP1505-EB

    ISBN-EB: 978-0-8031-8007-9

    ISBN-13: 978-0-8031-4514-6