Flow and Fracture of Metals and Alloys in Nuclear Environments

    Committee E10
    Published: 1965

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    Table of Contents

    Weber C.

    Mechanisms of Radiation Damage in Reactor Materials
    Brinkman J., Wiedersich H.

    Mechanisms of Radiation-Induced Mechanical Property Changes
    Barnes R.

    Irradiation Hardening and Embrittlement in Body-Centered Cubic Transition Metals
    Johnson A., Sargent G., Wronski A.

    Computer Studies of Neutron Irradiation and Annealing in Finite BCC Iron Specimens
    Beeler J.

    Effects of Irradiation in Iron and Steels
    Eyre B., Harries D.

    Low-Temperature Embrittlement of Iron, Iron Alloys, and Steels by Neutron Irradiations
    Chow J., McRickard S.

    Effect of Irradiation on Bend Transition Temperatures of Molybdenum- and Columbium-Base Alloys
    McCoy H., Weir J.

    Irradiation Effects on High-Temperature Reactor Structural Metals
    Claudson T., Pessl H.

    Recovery of Defects in Neutron-Irradiated Tungsten
    Moteit J., Smith J.

    The Nature and Annealing Behavior of Irradiation Damage in Molybdenum
    Eyre B., Roberts A.

    Effects of Irradiation in Austenitic Steels and Other High-Temperature Alloys
    Harries D., Pfeil P.

    The Flow and Fracture Properties of Unirradiated Stainless Steels
    Beeghly H.

    The Combined Effects of Temperature and Irradiation on the Mechanical Properties of Austenitic Stainless Steels
    Bement A., Hoagland R., Irvin J.

    The Effect of Irradiation Temperature on the Post-Irradiation Stress-Strain Behavior of Stainless Steel
    Martin W., Weir J.

    In-Reactor Stress-Rupture Properties of a 20Cr-25Ni, Columbium-Stabilized Steel
    Venard J., Weir J.

    New Information on Neutron Embrittlement and Embrittlement Relief of Reactor Pressure Vessel Steels
    Hawthorne J., Steele L.

    In-Depth Embrittlement of a Simulated Pressure Vessel Wall Of A302-B Steel
    Serpan C., Steele L.

    Strain-Cycle Phenomena In Thin-Wall Tubing

    Effects of Irradiation on A302-B Steel Subjected to a Multiaxial Stress Distribution
    Flynn P., Trozera T.

    In-Reactor Studies of Low-Cycle Fatigue Properties of a Nuclear Pressure Vessel Steel
    Hawthorne J., Steele L.

    Effects of Neutron Irradiation on the Flow and Fracture Behavior of Zircaloy-2
    Bement A., Hoagland R., Tobin J.

    In-Reactor Creep of Cold-Worked Zircaloy-2
    Holmes J., Nyman D., Tobin J., Williams J.

    Gas Formation and Compression Fractures in Irradiated Beryllium

    The Use of Materials Properties by the Reactor Vessel Designer
    Langer B.

    The Significance of Recent Developments in Fracture Mechanics In Great Britain In Relation To The Safety Of Reactor Pressure Vessels
    Irvine W.

    The Important Materials Parameters Affecting the Performance of Nuclear Reactor Pressure Vessels
    Wylie R.

    Crack Propagation Tests on Zircaloy-2 Reactor Pressure Tubing in Both the Normal and Hydrided Conditions
    Aungst R., Defferding L.

    Insurance Aspects of Radiation Damage in Reactor Structures
    Catudal F.

    Committee: E10

    DOI: 10.1520/STP380-EB

    ISBN-EB: 978-0-8031-6007-1

    ISBN-13: 978-0-8031-6161-0

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