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    Zirconium in the Nuclear Industry: Eighth International Symposium

    Eucken CM, Van Swam LFP
    Published: 1989

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    Topics include:

    • Behavior of Pressure Tubes

    • Corrosion

    • Nodular Corrosion

    • Basic Metallurgy

    • Mechanical Behavior, Stress Corrosion, and Fatigue

    • Creep and Growth

    Corrosion behavior is given special emphasis.

    Table of Contents

    Corrosion and Hydriding of N Reactor Pressure Tubes

    Oxidation and Deuterium Uptake of Zr-2.5Nb Pressure Tubes in CANDU-PHW Reactors

    Evaluation of Zircaloy-2 Pressure Tubes from NPD

    Growth, Fracture, and Nondestructive Evaluation of Hydride Blisters in Zr-2.5 Nb Pressure Tubes

    Effects of Hydride Morphology on Zr-2.5Nb Fracture Toughness

    Effects of Loading and Thermal Maneuvers on Delayed Hydride Cracking in Zr-2.5 Nb Alloys

    Influence of Chemical Composition on Uniform Corrosion of Zirconium-Base Alloys in Autoclave Tests

    Correlation Between 400°C Steam Corrosion Behavior, Heat Treatment, and Microstructure of Zircaloy-4 Tubing

    Influence of the Manufacturing Process on the Corrosion Resistance of Zircaloy-4 Cladding

    A Laboratory Method to Predict Hydriding Properties of Zirconium Alloys Under Irradiation

    Development of a Mechanistic Model to Assess the External Corrosion of the Zircaloy Claddings in PWRs

    Lithium Uptake and the Accelerated Corrosion of Zirconium Alloys

    Microstructure and Corrosion Studies for Optimized PWR and BWR Zircaloy Cladding

    Corrosion Performance of Zircaloy-2 and Zircaloy-4 PWR Fuel Cladding

    Development of a Cladding Alloy for High Burnup

    Enhanced Low-Temperature Oxidation of Zirconium Alloys Under Irradiation

    Internal Hydriding in Irradiated Defected Zircaloy Fuel Rods

    A Systematic Survey of the Factors Affecting Zircaloy Nodular Corrosion

    Corrosion Performance Ranking of Zircaloy-2 for BWR Applications

    Influence of Chemical Composition and Manufacturing Variables on Autoclave Corrosion of the Zircaloys

    Effects of Alloying Element Distribution on the Nodular Corrosion of Zircaloy-2

    Electron Microscopy Study of Oxide Films Formed on Zircaloy-2 in Superheated Steam

    Heterogeneous Scale Growth During Steam Corrosion of Zircaloy-4 and 500°C

    Automatic System for Measuring the Zirconium Liner and Zircaloy-2 Thickness of Zirconium Liner Tubes

    Solubility Limits and Formation of Intermetallic Precipitates in ZrSnFeCr Alloys

    Direct Measurement of Matrix Composition in Zircaloy-4 by Atom Probe Microanalysis

    Diffusion of 3D Transition Elements in α-Zr and Zirconium Alloys

    Beta-Quenched Zircaloy-4: Effects of Thermal Aging and Neutron Irradiation

    Intermetallic Precipitates in Zirconium-Niobium Alloys

    Magnetic Study of Zircaloy

    Oxidation Kinetics and Auger Microprobe Analysis of Some Oxidized Zirconium Alloys

    Simulated Fuel Expansion Testing of Zircaloy Tubing

    Link Between Stress Corrosion and Corrosion-Fatigue Behavior of Zircaloy in an Iodine Environment

    Effects of Irradiation and Hydriding on the Mechanical Properties of Zircaloy-4 at High Fluence

    Applications of Crystallographic Textures of Zirconium Alloys in the Nuclear Industry

    Stress Versus Strain Rate Characteristics of Zircaloy Cladding Tubes Subjected to Various Deformation Paths

    The Influence of Tin Content on the Thermal Creep of Zircaloy-4

    Effects of High Neutron Fluences on Microstructure and Growth of Zircaloy-4

    Accelerated Irradiation Growth of Zirconium Alloys

    Creep Behavior of Zircaloy Cladding Under Variable Conditions

    Effects of Microstructural Factors on Irradiation Growth in Zirconium-Niobium Alloys

    The Effect of Temperature on the Irradiation Growth of Cold-Worked Zr-2.5 Nb

    Discussion Section

    Discussion Section

    Committee: B10

    DOI: 10.1520/STP1023-EB

    ISBN-EB: 978-0-8031-5084-3

    ISBN-13: 978-0-8031-1199-8