Effects of Radiation on Structural Metals

    Committee E-10
    Published: 1967

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    Table of Contents


    General Discussion

    Effect of Nitrogen on the Mechanical Properties of Neutron-Irradiated Pure Iron

    Effects of Heat-Treatment and Irradiation on the High Temperature Tensile Properties of Austenitic Stainless Steels

    Engineering Significance of Ferrite Grain Size on the Radiation Sensitivity of Pressure Vessel Steels

    Effects of Neutron Irradiation on the Elevated Temperature Mechanical Properties of Nickel-Base and Refractory Metal Alloys

    Irradiation Effects on the Mechanical Properties of Vanadium-Base Alloys

    Irradiation Damage in Mild Steel: A Comparison of Crack Arrest Test and Charpy Criteria and Influence of Neutron Spectrum

    Gas Release and Compression Properties in Beryllium Irradiated at 600 and 750 C

    Creep of Annealed Type 304 Stainless Steel During Irradiation and Its Engineering Significance

    An Electron Microscope Investigation of High-Temperature Embrittlement of Irradiated Stainless Steels

    Review of Swedish Work on Irradiation Effects in Canning and Core Support Materials

    Review of Swedish Work on Irradiation Effects in Pressure Vessel Steels and on Significance of Data Obtained

    An Evaluation of Radiation Damage to Reactor Vessel Steels Using Both Transition Temperature and Fracture Mechanics Approaches

    Nature of Radiation Damage to Engineering Properties of Various Stainless Steel Alloys

    Applications of Fracture Mechanics in Evaluating Initiation and Propagation of Brittle Fracture in Reactor Structural Components

    Neutron Irradiation Embrittlement of Several Higher Strength Steels

    Implications of Embrittlement During the Life of a Zirconium Pressure Tube Reactor

    Properties of Irradiated Materials Needed for the Design of Reactor Vessels. Part I, Water Cooled Reactors

    Fatigue Properties of Irradiated Pressure Vessel Steels

    Solutions to the Problems of High-Temperature Irradiation Embrittlement

    Improved Postirradiation Tensile and Stress-Rupture Properties of Hastelloy X-280

    Effect of Neutron Irradiation on Mechanical Properties of AISI Type 347 Stainless Steel

    Effects of Neutron Irradiation on Creep-Rupture Properties of W-25RE Alloy

    Metallurgical Variables as Possible Factors Controlling Irradiation Response of Structural Steels

    Dose Rate, Annealing, and Stress Relaxation Studies of Radiation Hardening in Iron

    Damaging Neutron Exposure Criteria for Evaluating the Embrittlement of Reactor Pressure Vessel Steels in Different Neutron Spectra

    Cryogenic Radiation Effects on NERVA Structural Materials

    Plastic Stability of Zr-2 Fuel Cladding

    Influence of Boron on the Creep Rupture Properties of a Neutron Irradiated Precipitation Hardening Iron Base Alloy

    Role of Pressure Vessel Surveillance Programs in Power Reactors: Summary and Analysis of Asme Panel Discussion

    Committee: E10

    DOI: 10.1520/STP426-EB

    ISBN-EB: 978-0-8031-6024-8

    ISBN-13: 978-0-8031-6178-8

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