STP1023

    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
    Boyd S., Johnson A., Lanning D., Trimble D.

    Oxidation and Deuterium Uptake of Zr-2.5Nb Pressure Tubes in CANDU-PHW Reactors
    Chow C., Manolescu A., Shanahan M., Urbanic V., Warr B.

    Evaluation of Zircaloy-2 Pressure Tubes from NPD
    Causey A., Cheadle B., Chow P., Coleman C., Davies P., McManus M., Rodgers D., Sagat S., van Drunen G.

    Growth, Fracture, and Nondestructive Evaluation of Hydride Blisters in Zr-2.5 Nb Pressure Tubes
    Leger M., Moan G., Wallace A., Watson N.

    Effects of Hydride Morphology on Zr-2.5Nb Fracture Toughness
    Lepik O., Shek G., Wallace A.

    Effects of Loading and Thermal Maneuvers on Delayed Hydride Cracking in Zr-2.5 Nb Alloys
    Graham D., Shek G.

    Influence of Chemical Composition on Uniform Corrosion of Zirconium-Base Alloys in Autoclave Tests
    Eucken C., Finden P., Trapp-Pritsching S., Weidinger H.

    Correlation Between 400°C Steam Corrosion Behavior, Heat Treatment, and Microstructure of Zircaloy-4 Tubing
    Andersson T., Thorvaldsson T., Wardle A., Wilson A.

    Influence of the Manufacturing Process on the Corrosion Resistance of Zircaloy-4 Cladding
    Charquet D., Schemel J., Wadier J.

    A Laboratory Method to Predict Hydriding Properties of Zirconium Alloys Under Irradiation
    Gerber F., Johnson A., Lanning D., Levy I., Trimble D.

    Development of a Mechanistic Model to Assess the External Corrosion of the Zircaloy Claddings in PWRs
    Beslu P., Billot P., Giordano A., Thomazet J.

    Lithium Uptake and the Accelerated Corrosion of Zirconium Alloys
    Ling V., Precoanin N., Ramasubramanian N.

    Microstructure and Corrosion Studies for Optimized PWR and BWR Zircaloy Cladding
    Garzarolli F., Steinberg E., Weidinger H.

    Corrosion Performance of Zircaloy-2 and Zircaloy-4 PWR Fuel Cladding
    Andersson T., Pettersson H., Rudling P., Thorvaldsson T.

    Development of a Cladding Alloy for High Burnup
    Balfour M., Kilp G., Roberts E., Sabol G.

    Enhanced Low-Temperature Oxidation of Zirconium Alloys Under Irradiation
    Cox B., Fidleris V.

    Internal Hydriding in Irradiated Defected Zircaloy Fuel Rods
    Clayton J.

    A Systematic Survey of the Factors Affecting Zircaloy Nodular Corrosion
    Abe K., Aoki T., Fujibayashi T., Hattori T., Inagaki M., Kodama T., Murota K., Ogata K., Okubo T., Yoshitsugu M.

    Corrosion Performance Ranking of Zircaloy-2 for BWR Applications
    Machiels A., Rudling P.

    Influence of Chemical Composition and Manufacturing Variables on Autoclave Corrosion of the Zircaloys
    Finden P., Graham R., Tosdale J.

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

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

    Heterogeneous Scale Growth During Steam Corrosion of Zircaloy-4 and 500°C
    Charquet D., Tricot R., Wadier J.

    Automatic System for Measuring the Zirconium Liner and Zircaloy-2 Thickness of Zirconium Liner Tubes
    Honji M., Hyodo S., Morimoto Y., Sakamoto T.

    Solubility Limits and Formation of Intermetallic Precipitates in ZrSnFeCr Alloys
    Charquet D., Gros J., Hahn R., Ortlieb E., Wadier J.

    Direct Measurement of Matrix Composition in Zircaloy-4 by Atom Probe Microanalysis
    Andrén H., Wadman B.

    Beta-Quenched Zircaloy-4: Effects of Thermal Aging and Neutron Irradiation
    Adamson R., Yang W.

    Intermetallic Precipitates in Zirconium-Niobium Alloys
    Meng X., Northwood D.

    Magnetic Study of Zircaloy
    Miyake C., Takamiya T.

    Oxidation Kinetics and Auger Microprobe Analysis of Some Oxidized Zirconium Alloys
    Ploc R.

    Simulated Fuel Expansion Testing of Zircaloy Tubing
    Foster J., Leasure R.

    Link Between Stress Corrosion and Corrosion-Fatigue Behavior of Zircaloy in an Iodine Environment
    Lemaignan C., Schuster I.

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

    Applications of Crystallographic Textures of Zirconium Alloys in the Nuclear Industry
    Murty K.

    Stress Versus Strain Rate Characteristics of Zircaloy Cladding Tubes Subjected to Various Deformation Paths
    Okubo T., Suzuki H.

    The Influence of Tin Content on the Thermal Creep of Zircaloy-4
    Baty D., McInteer W., Stein K.

    Effects of High Neutron Fluences on Microstructure and Growth of Zircaloy-4
    Basso H., Dewes P., Garzarolli F., Maussner G.

    Accelerated Irradiation Growth of Zirconium Alloys
    Fidleris V., Gilbert R., Griffiths M.

    Creep Behavior of Zircaloy Cladding Under Variable Conditions
    Matsuo Y.

    Effects of Microstructural Factors on Irradiation Growth in Zirconium-Niobium Alloys
    Fuse M., Sadaoka N.

    The Effect of Temperature on the Irradiation Growth of Cold-Worked Zr-2.5 Nb
    Fleck R., Holt R.

    Discussion Section

    Author Index

    Subject Index


    Committee: B10

    Paper ID: STP1023-EB

    DOI: 10.1520/STP1023-EB

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

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

    ASTM International is a member of CrossRef.

    0-8031-1199-1
    978-0-8031-1199-8
    STP1023-EB