Irradiation Effects on The Microstructure and Properties of Metals

    Shober FR
    Published: 1976

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    An absolute must for anyone in the nuclear industry. Twenty-nine papers cover irradiation creep and stress relaxation; simulation; and embrittlement of pressure vessel steels, as well as mechanical properties, microstructure and void growth.

    Table of Contents

    Shober F.

    Effects of Prior Stress History on Irradiation-Induced Creep
    Wire G.

    Analysis of In-Reactor Stress Relaxation Using Irradiation Creep Models
    Foster J.

    Dynamic Strain-Aging and Neutron Irradiation in Mild Steel
    Hall E., Murty K.

    Swelling and Tensile Property Changes in Neutron-Irradiated Type 316 Stainless Steel
    Garr K., Pard A.

    Effect of Fast Reactor Irradiation on the Tensile Properties of 20 Percent Cold-Worked Type 316 Stainless Steel
    Fish R., Watrous J.

    Mechanical Properties of Fast Reactor Fuel Cladding for Transient Analysis
    Hunter C., Johnson G.

    Tensile Properties of Fast Reactor Irradiated Type 304 Stainless Steel
    Fish R., Hunter C.

    Effects of Neutron Irradiation on Microstructure and Mechanical Properties of Nimonic PE-16
    Bloom E., Clausing R., Sklad P.

    Irradiation and Thermal Effects on the Tensile Properties of Inconel-718
    Knecht R., Steichen J., Ward A.

    Tensile and Hardness Property Evaluations of Irradiated Zircaloy Cladding Under Off-Normal and Transient Conditions
    Bauer A., Lowry L., Perrin J.

    Neutron Energy Dependent Damage Functions for Tensile Properties of 20 Percent Cold-Worked Type 316 Stainless Steel
    Simons R.

    Swelling Simulation Studies of Type 316 Stainless Steel
    Appleby W., Ellis J., Lauritzen T.

    Development and Evaluation of a Stress-Free Swelling Correlation for 20 Percent Cold-Worked Type 316 Stainless Steel
    Garner F., Guthrie G., Laidler J.

    Swelling Behavior of Commercial Ferritic Alloys, EM-12 and HT-9, as Assessed by Heavy Ion Bombardment
    Malmberg P., Smidt F., Sprague J., Westmoreland J.

    Observation of Defect Clusters of Columbium and Columbium Alloys In Situ Irradiated Under a High-Voltage Electron Microscope
    Igata N., Murakami H., Watari F.

    Void Growth Suppression by Dislocation Impurity Atmospheres
    Green W., Weertman J.

    Dependence of Void Swelling on the Electron Vacancy Concentration
    Watkin J.

    Microstructure and Mechanisms of Ion-Simulated Irradiation-Induced Creep of Nickel
    Hendrick P., Michel D., Pieper A.

    Effects of Interstitial Solutes on the Microstructures of Self-Ion Irradiated Vanadium
    Agarwal S., Potter D., Taylor A.

    Swelling and Gamma-Prime Particle Stability of Ion-Bombarded Iron-Chromium-Nickel Alloys
    Bajaj R., Baron I., Bleiberg M., Chang A., Chickering R., Diamond S.

    Effect of Ion Irradiation on the Microstructure of an Iron-Nickel-Chromium Alloy
    Malmberg P., Smidt F., Sprague J., Westmoreland J.

    Microstructural Changes in Ion-Irradiated Commercial Alloys
    Bell W., Darlin E., Lauritzen T., Warner R.

    Nickel-Ion Damage in a Precipitation-Hardened Nickel-Aluminum
    Kirchner L., Kulcinski G., Smidt F., Sprague J., Westmoreland J.

    Fracture Mechanics Characterization of the Trino Reactor Vessel Material
    Davidson J., Galliani M., Mager T.

    Evaluation of the Maine Yankee Reactor Beltline Materials
    Sheckherd J., Smith R., Wullaert R.

    Evaluation of the Effect of Chemical Composition on the Irradiation Sensitivity of Reactor Vessel Weld Metal
    Biemiller E., Byrne S.

    Annealing of Irradiation Damage in High-Copper Ferritic Steels
    Phillips J., Shogan R., Spitznagel J.

    Displacement Spike Annealing in Iron at Reactor Temperatures
    Beeler J., Beeler M.

    Neutron Displacement Damage Cross Sections for Structural Metals
    Doran D., Graves N.


    Committee: E10

    DOI: 10.1520/STP611-EB

    ISBN-EB: 978-0-8031-5543-5

    ISBN-13: 978-0-8031-0388-7

    ASTM International is a member of CrossRef.