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    Irradiation Effects in Structural Alloys for Thermal and Fast Reactors

    Committee E-10 on Radioisotopes and Radiation Effects
    Published: 1969

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    Table of Contents


    The Effect of Cold Work, Thermal Treatment, and Neutron Irradiation on the Fracture Toughness of Zircaloy-2

    Comparison of In-Reactor Creep and Postirradiation Creep Tests of Structural Materials for Nuclear Applications

    High-Temperature Tensile Properties of Unirradiated and Thermal Reactor Irradiated Nimonic PE16

    Irradiation-Induced Embrittlement in Stainless Steel at Elevated Temperature

    Irradiation Tests of Several Steels for Reactor Pressure Vessels

    Initial Assessments of Notch Ductility Behavior of A533 Pressure Vessel Steel with Neutron Irradiation

    Notch Ductility, Tensile and Neutron Spectrum Analyses of PM-2A Reactor Pressure Vessel

    Irradiation Effects in Pressure Vessel Materials for Steam-Cooled Fast Reactors

    The Effect of Substructure on the Biaxial Strength and Irradiation Stability of ASTM A 302 Grade B Steel

    Effects of Interstitial Elements on Radiation Hardening in Mild Steels

    Radiation Hardening and Embrittlement in a Reactor Pressure Vessel Steel

    Development of Austenitic Stainless Steels with Improved Resistance to Elevated-Temperature Irradiation Embrittlement

    Development of a Titanium-Modified Hastelloy N with Improved Resistance to Radiation Damage

    Effects of Yttrium on the Structure and Post-Irradiation Tensile Properties of an Iron-Chromium-Aluminum Alloy

    Development of Fuel Cladding for Fast Reactors

    Effect of Irradiation on Mechanical Properties of Cobalt-Base Alloys

    Neutron Dosimetry for Fast-Reactor Irradiation and Surveillance Testing

    High-Temperature Embrittlement of AISI Type 316 Austenitic Stainless Steels after Irradiation

    Postirradiation Tensile Behavior of 300 Series Stainless Steels

    Multiaxial In-Reactor Stress-Rupture Strength of Stainless Steels and a Nickel Alloy

    Comparison of Radiation Damage Studies and Fuel Cladding Performance for lncoloy-800

    Effects of Neutron Irradiation on Creep-Rupture Properties of Type 316 Stainless Steel Tubes

    Committee: E10

    DOI: 10.1520/STP457-EB

    ISBN-EB: 978-0-8031-6036-1

    ISBN-13: 978-0-8031-6190-0