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    Properties of Reactor Structural Alloys After Neutron or Particle Irradiation

    Baroch CJ
    Published: 1975

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    The seventh ASTM International Symposium on Effects of Radiation on Structural Materials was held in Gatlinburg, Tenn., 11-13 June 1974. Committee E10 on Nuclear Applications and Measurement of Radiation Effects sponsored the symposium. C. J. Baroch, Babcock and Wilcox Company, presided as symposium chairman, and F. R. Shober, Westinghouse Hanford Company, served as symposium co-chairman.

    Table of Contents










    General Discussion

    Influence of Defects in Body-Centered Cubic Iron on Simulated Low-Energy Displacement Cascades

    Decrease of Ductility Upon Neutron Irradiation in Iron Alloys and Columbium

    Interaction of Strain and Radiation Damages in a Pressure Vessel Steel

    Strength and Notch Ductility of Selected Structural Alloys After High Fluence 550°F (288°C) Irradiation

    Reactor Vessel Material Surveillance Program

    Evaluation of Commercial Production A533-B Plates and Weld Deposits Tailored for Improved Radiation Embrittlement Resistance

    Effect of Impurity Concentration on the Change in Fracture Toughness of AISI Type 403 Stainless Steel with Fast Neutron Radiation

    Radiation Damage and Fatigue Evaluation of Reactor End Fittings

    Effect of Irradiation at 130, 650, and 775°F on Tensile Properties of Zircaloy-4 at 70, 650, and 775°F

    Effect of Neutron Irradiation on Types 316 and 321 and Sandvik 12R72 Stainless Steels

    Fatigue Behavior and Microstructure of Neutron Irradiated Thin Section Type 304 Stainless Steel at Elevated Temperatures

    Fatigue and Creep-Fatigue Behavior of Irradiated and Unirradiated Type 308 Stainless Steel Weld Metal at Elevated Temperatures

    Fatigue Crack Propagation in Fast Neutron Irradiated Stainless Steels and Welds

    Dose Dependence of Irradiation Creep of Zircaloy-2

    Improvement of Creep Properties in a Helium Injected Austenitic Stainless Steel

    Creep and Swelling Deformation in Structural Materials During Fast-Neutron Irradiation

    Multiaxial Primary Irradiation Creep Equations for Reactor Structural Materials

    Surface Reaction Limited Void Growth

    Spectral Effects in Neutron and Charged Particle Irradiations

    Postirradiation Properties of the 6061-T6 Aluminum High Flux Isotope Reactor Hydraulic Tube

    Comparison of Displacement and Gas Production Rates in Current Fission and Future Fusion Reactors

    Helium Mobility and Bubble Formation in Type 316 Stainless Steel, Aluminum, and Vanadium

    Irradiation-Induced Swelling Variations Resulting from Compositional Modifications of Type 316 Stainless Steel

    Effect of the Degree of Cold Work on the Irradiation-Induced Swelling of Type 316 Stainless Steel

    Dimensional Stability of Neutron Irradiated Molybdenum

    Dimensional Stability of Tantalum During Fast Neutron Irradiation

    Influence of High Voltage Electron Microscope Irradiation on Neutron-Produced Microstructures in Stainless Steels

    Swelling in Electron-Irradiated Type 316 Stainless Steel

    Void Formation in Cold-Worked Type 316 Stainless Steel Irradiated with 1-MeV Protons

    Void Formation in an Ion Bombarded Cold-Worked Stainless Steel

    Effect of Irradiation Parameters on Nickel-Ion Damage in Nickel

    Void Swelling in the Iron-Chromium-Nickel System—A Survey by Nickel Ion Bombardment

    Swelling Resistance Induced by Grain Refinement and Particle Dispersion in Austenitic Stainless Steel During High Energy Electron Irradiation

    Development Programs on Irradiation Embrittlement of Low Alloy Pressure Vessel Steels in the Federal Republic of Germany

    Swelling and Irradiation Induced Microstructural Changes in Nickel-Based Alloys

    Irradiated Steels Behavior in Long-Term Load Tests

    Motion of Dislocation in Stainless Steel During the Fast Neutron Irradiation

    Committee: E10

    DOI: 10.1520/STP570-EB

    ISBN-EB: 978-0-8031-4653-2

    ISBN-13: 978-0-8031-0539-3