STP1132

    Zirconium in the Nuclear Industry: Ninth International Symposium

    Eucken CM, Garde AM
    Published: 1991


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    36 papers from the most significant body of technical literature on zirconium alloy properties. Sections include: Fabrication, Mechanical Properties, and Corrosion.


    Table of Contents

    Discussion

    Discussion

    Discussion

    Discussion

    Discussion

    Discussion

    Discussion

    Zirconium-Alloy Corrosion: A Review Based on an International Atomic Energy Agency (IAEA) Meeting

    Deformability of Zirconium-Lined Cladding Tube in Cold Pilgering

    Processing Map and Hot Working Characteristics of Zircaloy-2

    Establishing Statistical Models of Manufacturing Parameters: Zircaloy-4 Cladding Tube Properties

    Texture Control in Zircaloy Tubing Through Processing

    Fracture Toughness Evaluation of Heat-Treated Zr-2.5Nb Pressure Tubes

    Effect of Tensile Deformation on Crystallographic Texture in Zircaloy Sheet

    Correlation of Microstructure and Mechanical Properties of Zr-Sn Alloys

    Microstructure of Zr-2.5Nb Alloy Pressure Tubing

    Growth in Zircaloy-4 Fuel Clad Arising from Oxidation at Temperatures in the Range 623 to 723 K

    Effects of Recrystallization and Neutron Irradiation on Creep Anisotropy of Zircaloy Cladding

    The Contribution of Irradiation Growth to Pressure Tube Deformation

    Fatigue Behavior of Neutron Irradiated Zircaloy-2 Fuel Cladding Tubes

    Fracture Toughness of Irradiated Zr-2.5Nb Pressure Tubes from CANDU Reactors

    Controlled Composition Zircaloy-2 Uniform Corrosion Resistance

    Influence of Alloy Composition and Processing on the Nodular Corrosion Resistance of Zircaloy-2

    Investigation of Nodular Corrosion Mechanism for Zircaloy Products

    Development of Highly Corrosion Resistant Zirconium-Base Alloys

    Effect of Alloying Elements on Uniform Corrosion Resistance of Zirconium-based Alloys in 360°C Water and 400°C Steam

    Oxide Growth Mechanism on Zirconium Alloys

    Raman Spectroscopy Study of the Tetragonal-to-monoclinic Transition in Zirconium Oxide Scales and Determination of Overall Oxygen Diffusion by Nuclear Microanalysis of O18

    Effect of Alloying Elements in Zircaloy on Photo-Electrochemical Characteristics of Zirconium Oxide Films

    Microanalysis of the Matrix and the Oxide-Metal Interface of Uniformly Corroded Zircaloy

    Precipitate Behavior in Zircaloy-2 Oxide Films and Its Relevance to Corrosion Resistance

    Corrosion-Electrochemical Properties of Zirconium Intermetallics

    Comparison of Zircaloy Corrosion Models from the Evaluation of In-Reactor and Out-of-Pile Loop Performance

    Enhancement of Aqueous Corrosion of Zircaloy-4 Due to Hydride Precipitation at the Metal-Oxide Interface

    Corrosion of Zircaloy in the Presence of LiOH

    Lithium Uptake and the Corrosion of Zirconium Alloys in Aqueous Lithium Hydroxide Solutions

    Corrosion of Zircaloy-4 Pwr Fuel Cladding in Lithiated and Borated Water Environments

    Effects Of LiOH on Pretransition Zirconium Oxide Films

    Investigation of Variables That Influence Corrosion of Zirconium Alloys during Irradiation

    Characteristics of Autoclave and In-Reactor Nodular Corrosion of Zircaloys

    Amorphization of Precipitates in Zircaloy under Neutron and Charged-Particle Irradiation

    Oxide Characteristics and Their Relationship to Hydrogen Uptake in Zirconium Alloys

    The Corrosion of Zircaloy-4 Fuel Cladding in Pressurized Water Reactors

    Appendix: List of Poster Presenations

    Author Index

    Subject Index


    Committee: B10

    DOI: 10.1520/STP1132-EB

    ISBN-EB: 978-0-8031-5177-2

    ISBN-13: 978-0-8031-1463-0

    ASTM International is a member of CrossRef.

    0-8031-1463-X
    978-0-8031-1463-0
    STP1132-EB