STP458

    Applications-Related Phenomena in Zirconium and its Alloys

    Committee B-10

    Pages: 376

    Published: 1969

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    Table of Contents

    The Effect of Texture and Strain Aging on Creep of Zircaloy-2
    Fidleris V.

    In-Reactor Creep of Zirconium-Alloy Tubes and Its Correlation with Uniaxial Data
    Ibrahim E.

    Texture Changes Produced During Zircaloy-4 Tubing Fabrication: From Forged Billet to Finished Tubing
    Hobson D.

    Texture Development and Texture Gradients in Zircaloy Tubing
    Rittenhouse P., Tenckhoff E.

    The Anisotropy of Fracture Ductility in Flat Tension-Test Bars of Alpha Zirconium Alloy
    Cheadle B., Ells C.

    The Mechanical Properties of Zircaloy-2 Tubing Containing Circumferentially Aligned Hydride
    Slattery G.

    Texture Development and Phase Stability of 0.5Cu-0.5Mo Zirconium During Fabrication to Sheet Form
    Kaufmann P.

    Fatigue-Crack Growth and Propagation in 2.5Nb Zirconium Alloy Pressure Tubing
    Pankaskie P.

    Embrittlement of Zircaloy-2 Pressure Tubes
    Cowan A., Parry G., Pickles B., Watkins B.

    The Effect of Orientation of Hydride Precipitates on the Fracture Toughness of Cold-Rolled Zircaloy-2 and 2.5Nb Zirconium
    Aitchison I.

    Oxygen Embrittlement of Zirconium-Copper Alloys at High Temperatures
    Debray W., Kaden W.

    The Effect of Neutron Irradiation and Cold Work on the Strain-Aging Behavior of Zircaloy-2
    Rotsey W., Snowden K., Veevers K.

    Creep of Zirconium from 50 to 850 C
    Bement A., Duran S., Gilbert E.

    The Significance of Irradiation-Induced Creep on Reactor Performance of a Zircaloy-2 Pressure Tube
    Watkins B., Wood D.

    The Effect of Texture on the Torsional Yielding of Zircaloy Tubing
    Rittenhouse P.

    Failure of Pressurized Zircaloy Tubes During Thermal Excursions in Steam and in Inert Atmospheres
    Emmerich K., Juenke E., White J.

    Corrosion and Failure Characteristics of Zirconium Alloys in High-Pressure Steam in the Temperature Range 400 to 500 C
    Johnson A.

    The Corrosion Behavior of 2.5Nb Zirconium Alloy
    LeSurf J.

    Effects of Nuclear Radiation on the Corrosion, Hydriding, and Oxide Properties of Six Zirconium Alloys
    Johnson A.

    Ozhennite 0.5 — Its Potential and Development
    Boulton J., Wright M.

    The Use of Hydrogen Getters for Prevention of Hydrogen Embrittlement in Zirconium-Alloy Fuel Cans
    Spalthoff W., Wilhelm H.

    Tension-Testing Variables in Zirconium
    Schemel J.

    Round-Robin Tests to Develop a Standard Autoclave Testing Procedure for Zirconium Alloys
    Bryant P.

    Neutrographic Hydrogen Determination in Zirconium Alloys
    Esch E., Klepfer H., Kosanke H.

    Discussion on the Effects of Machine Straightening on Hydride Orientation of Zircaloy-4 Tubing
    Rees T., Shaheen L.


    Committee: B10

    Paper ID: STP458-EB

    DOI: 10.1520/STP458-EB

    ISBN-EB: 978-0-8031-6037-8

    ISBN-PRINT: 978-0-8031-6191-7

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    0-8031-6191-3
    978-0-8031-6191-7
    STP458-EB