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
    Franklin D., Lang P.

    Deformability of Zirconium-Lined Cladding Tube in Cold Pilgering
    Abe H., Honji M., Kobayashi T., Konishi T., Tarui H.

    Processing Map and Hot Working Characteristics of Zircaloy-2
    Asundi M., Chakravartty J., Prasad Y.

    Establishing Statistical Models of Manufacturing Parameters: Zircaloy-4 Cladding Tube Properties
    Deshayes J., Pape J., Senevat J.

    Texture Control in Zircaloy Tubing Through Processing
    Cook C., Randall S., Sabol G., Sekera K.

    Fracture Toughness Evaluation of Heat-Treated Zr-2.5Nb Pressure Tubes
    Asada T., Chiba N., Kasai Y., Kimoto H.

    Effect of Tensile Deformation on Crystallographic Texture in Zircaloy Sheet
    Mahmood S., Murty K.

    Correlation of Microstructure and Mechanical Properties of Zr-Sn Alloys
    Asundi M., Banerjee S., Raman V., Wadekar S.

    Microstructure of Zr-2.5Nb Alloy Pressure Tubing
    Meng-Burany X., Northwood D., Warr B.

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

    Effects of Recrystallization and Neutron Irradiation on Creep Anisotropy of Zircaloy Cladding
    Mahmood S., Murty K.

    The Contribution of Irradiation Growth to Pressure Tube Deformation
    Fleck R., Holt R.

    Fatigue Behavior of Neutron Irradiated Zircaloy-2 Fuel Cladding Tubes
    Hayashi Y., Kubo T., Nakatsuka M.

    Fracture Toughness of Irradiated Zr-2.5Nb Pressure Tubes from CANDU Reactors
    Choubey R., Chow C., Coleman C., Davies P., Griffiths M., Hosbons R.

    Controlled Composition Zircaloy-2 Uniform Corrosion Resistance
    Eucken C., Graham R.

    Influence of Alloy Composition and Processing on the Nodular Corrosion Resistance of Zircaloy-2
    Bradley E., Nystöm A., Schemel J.

    Investigation of Nodular Corrosion Mechanism for Zircaloy Products
    Eucken C., Graham R., Wang C.

    Development of Highly Corrosion Resistant Zirconium-Base Alloys
    Isobe T., Matsuo Y.

    Effect of Alloying Elements on Uniform Corrosion Resistance of Zirconium-based Alloys in 360°C Water and 400°C Steam
    Abe K., Harada M., Kimpara M.

    Oxide Growth Mechanism on Zirconium Alloys
    Garzarolli F., Gros J., Seidel H., Tricot R.

    Raman Spectroscopy Study of the Tetragonal-to-monoclinic Transition in Zirconium Oxide Scales and Determination of Overall Oxygen Diffusion by Nuclear Microanalysis of O18
    Godlewski J., Gros J., Lambertin M., Wadier J., Weidinger H.

    Effect of Alloying Elements in Zircaloy on Photo-Electrochemical Characteristics of Zirconium Oxide Films
    Inagaki M., Kanno M., Maki H.

    Microanalysis of the Matrix and the Oxide-Metal Interface of Uniformly Corroded Zircaloy
    Andrén H., Wadman B.

    Precipitate Behavior in Zircaloy-2 Oxide Films and Its Relevance to Corrosion Resistance
    Kubo T., Uno M.

    Corrosion-Electrochemical Properties of Zirconium Intermetallics
    Cheliotis G., Maguire M., Ruhmann H., Weidinger H., Yau T.

    Comparison of Zircaloy Corrosion Models from the Evaluation of In-Reactor and Out-of-Pile Loop Performance
    Billot P., Giordano A.

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

    Corrosion of Zircaloy in the Presence of LiOH
    Busch R., Perkins R.

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

    Corrosion of Zircaloy-4 Pwr Fuel Cladding in Lithiated and Borated Water Environments
    Bramwell I., Parsons P., Tice D.

    Effects Of LiOH on Pretransition Zirconium Oxide Films
    Cox B., Wong Y.

    Investigation of Variables That Influence Corrosion of Zirconium Alloys during Irradiation
    Choubey R., Chow C., Urbanic V.

    Characteristics of Autoclave and In-Reactor Nodular Corrosion of Zircaloys
    Chung H., Jeong Y., Rheem K.

    Amorphization of Precipitates in Zircaloy under Neutron and Charged-Particle Irradiation
    Lefebvre F., Lemaignan C., Motta A.

    Oxide Characteristics and Their Relationship to Hydrogen Uptake in Zirconium Alloys
    Brennenstuhl A., Elmoselhi M., Lichtenberger P., McIntyre N., Newcomb S., Warr B.

    The Corrosion of Zircaloy-4 Fuel Cladding in Pressurized Water Reactors
    Shann S., Van Swam L.

    Appendix: List of Poster Presenations

    Author Index

    Subject Index


    Committee: B10

    Paper ID: STP1132-EB

    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