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    Zirconium in the Nuclear Industry: Tenth International Symposium

    Garde AM, Bradley ER
    Published: 1994

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    4 sections are devoted to various aspects of zirconium alloy corrosion: Hydrogen Effects; • Lithium Effects and Second-Phase Particles; • Oxide Characterization; • and In-Reactor Corrosion.

    The remaining sections include Pressure Tubes; Fabrication; and Mechanical Properties.

    Table of Contents

    Development of Zirconium-Barrier Fuel Cladding

    Zirconium Alloy Performance in Light Water Reactors: A Review of UK and Scandinavian Experience

    The Effect of Fluence and Irradiation Temperature on Delayed Hydride Cracking in Zr-2.5Nb

    A Study of the Hydrogen Uptake Mechanism in Zirconium Alloys

    Hydrogen Absorption Kinetics During Zircaloy Oxidation in Steam

    Scanning Electron Microscope Techniques for Studying Zircaloy Corrosion and Hydriding

    Growth and Characterization of Oxide Films on Zirconium-Niobium Alloys

    Correlation Between Irradiated and Unirradiated Fracture Toughness of Zr-2.5Nb Pressure Tubes

    Variability of Irradiation Growth in Zr-2.5Nb Pressure Tubes

    Change of Mechanical Properties by Irradiation and Evaluation of the Heat-Treated Zr-2.5Nb Pressure Tube

    On the Anisotropy of In-Reactor Creep of Zr-2.5Nb Tubes

    Fabrication of Zr-2.5Nb Pressure Tubes to Minimize the Harmful Effects of Trace Elements

    Modeling of Damage in Cold Pilgering

    Mitigation of Harmful Effects of Welds in Zirconium Alloy Components

    Fabrication Process of High Nodular Corrosion-Resistant Zircaloy-2 Tubing

    Corrosion Behavior of Zircaloy-4 Sheets Produced Under Various Hot-Rolling and Annealing Conditions

    Optimization of PWR Behavior of Stress-Relieved Zircaloy-4 Cladding Tubes by Improving the Manufacturing and Inspection Process

    Experimental and Theoretical Studies of Parameters that Influence Corrosion of Zircaloy-4

    Aqueous Chemistry of Lithium Hydroxide and Boric Acid and Corrosion of Zircaloy-4 and Zr-2.5Nb Alloys

    Corrosion Behavior of Irradiated Zircaloy

    Correlation of Transmission Electron Microscopy (TEM) Microstructure Analysis and Texture with Nodular Corrosion Behavior for Zircaloy-2

    Micro-Characterization of Corrosion Resistant Zirconium-Based Alloys

    An Experimental Investigation into the Oxidation of Zircaloy-4 at Elevated Pressures in the 750 to 1000°C Temperature Range

    Prediction of Creep Anisotropy in Zircaloy Cladding

    Microstructure and Properties of Corrosion-Resistant Zirconium-Tin-lron-Chromium-Nickel Alloys

    Fatigue Behavior of Irradiated and Unirradiated Zircaloy and Zirconium

    Effect of Irradiation on the Microstructure of Zircaloy-4

    Irradiation Effect on Fatigue Behavior of Zircaloy-4 Cladding Tubes

    Grain-by-Grain Study of the Mechanisms of Crack Propagation During Iodine Stress Corrosion Cracking of Zircaloy-4

    Microstructure of Oxide Layers Formed During Autoclave Testing of Zirconium Alloys

    Corrosion Performance of New Zircaloy-2-Based Alloys

    Examinations of the Corrosion Mechanism of Zirconium Alloys

    On the Initial Corrosion Mechanism of Zirconium Alloy: Interaction of Oxygen and Water with Zircaloy at Room Temperature and 450°C Evaluated by X-Ray Absorption Spectroscopy and Photoelectron Spectroscopy

    How the Tetragonal Zirconia is Stabilized in the Oxide Scale that is Formed on a Zirconium Alloy Corroded at 400°C in Steam

    Oxidation of Intermetallic Precipitates in Zircaloy-4: Impact of Irradiation

    Corrosion Optimized Zircaloy for Boiling Water Reactor (BWR) Fuel Elements

    In-Reactor Corrosion Performance of ZIRLO™ and Zircaloy-4

    Phenomenological Study of In-Reactor Corrosion of Zircaloy-4 in Pressurized Water Reactors

    Corrosion Behavior of Zircaloy-4 Cladding with Varying Tin Content in High-Temperature Pressurized Water Reactors

    Effects of Pressurized Water Reactor (PWR) Coolant Chemistry on Zircaloy Corrosion Behavior

    Committee: B10

    DOI: 10.1520/STP1245-EB

    ISBN-EB: 978-0-8031-5286-1

    ISBN-13: 978-0-8031-2011-2