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    Effects of Radiation on Structural Materials

    Sprague JA, Kramer David
    Published: 1979

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    This volume covers six subject areas: microstructure, fracture of thermal reactor materials, primary damage production and irradiation creep simulation, dosimetry and damage function analysis, mechanical properties and creep.

    Table of Contents



    Determination of the Nature of Neutron Irradiation-Induced Dislocation Loops in Magnesium Using Electron Irradiation in the Transmission Electron Microscope

    Radiation Effects on Molybdenum Alloys Bombarded by Electrons in a High-Voltage Electron Microscope

    Microstructural Development During Low-Dose Irradiation

    Neutron Irradiation-Induced Defect Structures in Zirconium

    Irradiation Growth in Zirconium and Its Alloys

    Dependence of Cavity Nucleation Density Upon Gas Implantation Rate and Its Importance in Dual-Beam Irradiation Conditions

    Response of Inconel 600 to Simulated Fusion Reactor Irradiation

    Effects of Neutron Irradiation on the Microstructure of Niobium and Niobium-Base Alloys

    Effects of Bombarding Ions on the Void Swelling Profile in Nickel

    Development of Physically Based Void Swelling Equations for Engineering and Design Use

    A Reassessment of the Role of Stress in Development of Radiation-Induced Microstructure

    Radiation-Induced Segregation in Nickel-Silicon Alloys

    An Example of Precipitate Stability in Reactor-Irradiated Nimonic PE16

    Dependence of Void Formation on Phase Stability in Neutron-Irradiated Type 316 Stainless Steel

    Evaluation of Commercial Production A533-B Steel Plates and Weld Deposits with Extra-Low Copper Content for Radiation Resistance

    An Empirical Evaluation of the Irradiation Sensitivity of Reactor Pressure Vessel Materials

    Irradiation Behavior of Nickel-Chromium-Molybdenum Type Weld Metal

    Exploratory Investigations of Cyclic Irradiation and Annealing Effects on Notch Ductility of A533-B Weld Deposits

    Effect and Possibilities of Irradiation Results Error Correction (Demonstrated on the Results of the IAEA Coordinated Program)

    Fracture Toughness of Irradiated Beryllium

    Irradiation Creep and Growth in Zirconium During Proton Bombardment

    Radiation Damage Effects in 16-MeV Proton and 14-MeV Neutron Irradiated Nickel and Niobium

    Helium Production in Fast Breeder Reactor Out-of-Core Structural Components

    Radiation Damage Function Analysis

    Solid-State Track Recorder Materials for Use in Light-Water-Reactor Pressure Vessel Surveillance Exposures

    Microstructure and Tensile Properties of Heavily Irradiated 1100-0 Aluminum

    Tensile Properties of Neutron-Irradiated 6061 Aluminum Alloy in Annealed and Precipitation-Hardened Conditions

    Tensile Property Correlations for Highly Irradiated 20 Percent Cold-Worked Type 316 Stainless Steel

    Low-Cycle Fatigue of Three Irradiated and Unirradiated Vanstar Alloys

    Effects of Neutron Irradiation and Fatigue on Ductility of Stainless Steel DIN 1.4948

    Estimates of Time-Dependent Fatigue Behavior of Type 316 Stainless Steel Subject to Irradiation Damage in Fast Breeder and Fusion Power Reactor Systems

    Fracture Toughness of Irradiated AISI 304 and 316L Stainless Steels

    Fracture Toughness of Irradiated Nimonic PE16 at High Temperatures

    Effects of Irradiation on the Mechanical Properties of Austenitic Stainless Steels Under Dynamic Loading

    Effects of Irradiation Temperature, Fluence, and Heating Rate on Postirradiation Flow Properties of Cladding Under Simulated Temperature Transient Heating and Deformation Conditions

    Effects of Irradiation Creep on Ex-Reactor Mechanical Properties

    Formulation of Constitutive Laws for Deformation During Irradiation

    Irradiation Creep in Bending of Cold-Worked AISI 316 Stainless Steel at Low Neutron Fluence

    A Comparison of Fuel Pin Deformations with Pressurized Tube Creep Tests

    Reduction of Irradiation-Induced Creep by Point-Defect Trapping

    Irradiation Creep Due to Stress-Induced Preferred Absorption of Point Defects in Zirconium Single Crystals

    In-Reactor Deformation and Fracture of Austenitic Stainless Steels


    Committee: E10

    DOI: 10.1520/STP683-EB

    ISBN-EB: 978-0-8031-5551-0

    ISBN-13: 978-0-8031-0327-6