STP824

    Zirconium in the Nuclear Industry

    Franklin DG, Adamson RB
    Published: 1984


      Format Pages Price  
    PDF (13M) $92   ADD TO CART
    Hardcopy (shipping and handling) $92   ADD TO CART
    Hardcopy + PDF Bundle - Save 25%
    (shipping and handling)
    $138.00   ADD TO CART


    Discusses zirconium extraction and reduction to tubes; recent work on basic properties; fracture properties, including stress-corrosion cracking and hydrogen cracking; high-temperature properties; texture-related work with special interest in creep and growth; and waterside corrosion.


    Table of Contents

    Introduction
    Adamson R., Franklin D.

    Discussion

    Discussion

    Discussion

    Discussion

    Discussion

    Discussion

    Discussion

    Discussion

    Discussion

    Discussion

    Summary
    Adamson R., Franklin D.

    Extractive Metallurgy of Zirconium—1945 to the Present
    Stephens W.

    New Process for Zirconium and Hafnium Separation
    Brun P., Moulin L., Thouvenin P.

    New Solvent Extraction Process for Zirconium and Hafnium
    Katoh Y., Miyazaki H., Takahashi M.

    Electron-Beam Remelting of Zircaloys
    Brown R., Mitchell A.

    Characteristics of Hydrostatically Extruded Zr-2.5Nb Alloy
    Jiaqi D., Jie Z., Tieqi Y., Wenxian H., Yan L., Yunxia Z., Zhenhe L.

    Pressure Tube Development for CANDU Reactors
    Cheadle B., Fleck R., Price E.

    Analytical Approaches and Experimental Verification to Describe the Influence of Cold Work and Heat Treatment on the Mechanical Properties of Zircaloy Cladding Tubes
    Schaa A., Steinberg E., Weidinger H.

    On-Line Ultrasonic Inside-Diameter Control System for Zircaloy Tube Etching
    Fujii N., Komatsu M., Kubota H., Tanaka Y.

    Variation in the Strain Anisotropy of Zircaloy with Temperature and Strain
    Hindle E., Worswick D.

    A Study on the Nonelastic Behavior of Zircaloy Fuel Cladding
    Okubo T., Suzuki H.

    Flow Softening and Anneal Hardening in Two-Phase Zr-2.5Nb
    Choubey R., Jonas J., Rizkalla A.

    On the Short-Time Recrystallization of Zircaloy-4 Above 600°C
    Bäro G., Nicoll A., Wessjohann H.

    Orientation of Hydrides in Zirconium Alloy Tubes
    Cheadle B., Coleman C., Ipohorski M.

    Correlation Between Fabrication Parameters, Microstructure, and Texture in Zircaloy Tubing
    Moulin L., Reschke S., Tenckhoff E.

    On the Texture Measurements for Zircaloy Cladding Tube
    Fujita K., Kakuma T., Kimpara M., Nagai N.

    Texture Effect of Zircaloy on Ultrasonic Velocity
    Honji M., Konishi T.

    In-Reactor Creep of Zr-2.5Nb
    Causey A., Holt R., MacEwen S.

    Influence of Metallurgical Condition on the In-Reactor Dimensional Changes of Zircaloy Fuel Rods
    Garde A., Garzarolli F., Manzel R., Smerd P.

    Deformation Characteristics of Cold-Worked and Recrystallized Zircaloy-4 Cladding
    Baty D., Clevinger G., Dietrich M., Papazoglou T., Pavinich W.

    Irradiation Creep and Growth During Proton and Neutron Bombardment of Zircaloy-2 Plate
    Chapman O., McElroy R., Sheldon B.

    Irradiation Growth of Annealed Zircaloy-2
    Darby E., Minty D., Williams J.

    Irradiation-Induced Dimensional Changes in Polycrystalline Iodide Zirconium and Zircaloy-2
    Rogerson A.

    Irradiation Growth in Zr-2.5Nb
    Fleck R., Léger M.

    High-Fluence Irradiation Growth of Zirconium Alloys at 644 to 725 K
    Adamson R., Fidleris V., Tucker R.

    Irradiation Growth of Zircaloy (LWBR Development Program)
    Willard H.

    Characterization of ZrO2 Films Formed In-Reactor and Ex-Reactor to Study the Factors Contributing to the In-Reactor Waterside Corrosion of Zircaloy
    Garde A., Garzarolli F., Smerd P., Stehle H.

    Improved Characterization of Aqueous Corrosion Kinetics of Zircaloy-4
    Peters H.

    Effect of Lithium Hydroxide on the Corrosion Behavior of Zircaloy-4
    McDonald S., Sabol G., Sheppard K.

    Application of Alternating-Current Impedance Measurements to Characterize Zirconium Alloy Oxidation Films
    Rosecrans P.

    Observations of Accelerated Hydriding in Zirconium Alloys
    Urbanic V.

    Out-of-Pile Nickel Alloy-Induced Accelerated Hydriding of Zircaloy Fasteners
    Clayton J.

    Modeling of Zircaloy Stress-Corrosion Cracking: Texture Effects and Dry Storage Spent Fuel Behavior
    Einziger R., Miller A., Tasooji A.

    Influence of Crystallographic Texture and Test Temperature on Initiation and Propagation of Iodine Stress-Corrosion Cracks in Zircaloy
    Knorr D., Pelloux R., Peltier J.

    Effect of Direction of Approach to Temperature on the Delayed Hydrogen Cracking Behavior of Cold-Worked Zr-2.5Nb
    Ambler J.

    Cracking Zirconium Alloys in Hydrogen
    Coleman C., Cox B.

    Effect of Bundle Size on Cladding Deformation in LOCA Simulation Tests
    Chapman R., Crowley J., Longest A.

    Deformation and Failure of Zircaloy Fuel Sheaths Under LOCA Conditions
    Sagat S., Sills H., Walsworth J.

    Estimation of Conservatism of Present Embrittlement Criteria for Zircaloy Fuel Cladding Under LOCA
    Furuta T., Kawasaki S., Uetsuka H.

    Out-of-Pile Experiments on the High-Temperature Behavior of Zircaloy-4 Clad Fuel Rods
    Hagen S.

    Comparison of High-Temperature Steam Oxidation Kinetics Under LWR Accident Conditions: Zircaloy-4 Versus Austenitic Stainless Steel No. 1.4970
    Leistikow S.

    Fuel Rod Deformation in LOCA and Severe Core Damage Accidents
    Burman D., Davis D., Hochreiter L., Lutz R.

    High-Temperature Oxidation of Zircaloy in Hydrogen-Steam Mixtures
    Chung H., Thomas G.

    Physical and Chemical Phenomena Associated with the Dissolution of Solid UO2 by Molten Zircaloy-4
    Hofmann P., Kerwin-Peck D., Nikolopoulos P.

    Index


    Committee: B10

    Paper ID: STP824-EB

    DOI: 10.1520/STP824-EB

    ISBN-EB: 978-0-8031-4895-6

    ISBN-13: 978-0-8031-0270-5

    ASTM International is a member of CrossRef.

    0-8031-0270-4
    978-0-8031-0270-5
    STP824-EB