STP683

    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

    Introduction
    Sprague J.

    Summary

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

    Radiation Effects on Molybdenum Alloys Bombarded by Electrons in a High-Voltage Electron Microscope
    Igata N., Itadani K., Kohyama A.

    Microstructural Development During Low-Dose Irradiation
    Hall B., Potter D.

    Neutron Irradiation-Induced Defect Structures in Zirconium
    Blake R., Farrell K., Jostsons A., Kelly P.

    Irradiation Growth in Zirconium and Its Alloys
    Northwood D.

    Dependence of Cavity Nucleation Density Upon Gas Implantation Rate and Its Importance in Dual-Beam Irradiation Conditions
    Bullough R., Hayns M., Wood M.

    Response of Inconel 600 to Simulated Fusion Reactor Irradiation
    Wiffen F.

    Effects of Neutron Irradiation on the Microstructure of Niobium and Niobium-Base Alloys
    Michel D., Smith H.

    Effects of Bombarding Ions on the Void Swelling Profile in Nickel
    Kulcinski G., Smith H., Whitley J., Wilkes P.

    Development of Physically Based Void Swelling Equations for Engineering and Design Use
    Bullough R., Hayns M.

    A Reassessment of the Role of Stress in Development of Radiation-Induced Microstructure
    Brager H., Garner F., Wolfer W.

    Radiation-Induced Segregation in Nickel-Silicon Alloys
    Okamoto P., Potter D., Rehn L., Wiedersich H.

    An Example of Precipitate Stability in Reactor-Irradiated Nimonic PE16
    Gelles D.

    Dependence of Void Formation on Phase Stability in Neutron-Irradiated Type 316 Stainless Steel
    Brager H., Garner F.

    Evaluation of Commercial Production A533-B Steel Plates and Weld Deposits with Extra-Low Copper Content for Radiation Resistance
    Byrne S., Hawthorne J., Koziol J.

    An Empirical Evaluation of the Irradiation Sensitivity of Reactor Pressure Vessel Materials
    Byrne S., Varsik J.

    Irradiation Behavior of Nickel-Chromium-Molybdenum Type Weld Metal
    Gerscha A., Klausnitzer E., Leitz C.

    Exploratory Investigations of Cyclic Irradiation and Annealing Effects on Notch Ductility of A533-B Weld Deposits
    Hawthorne J., Loss F., Watson H.

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

    Fracture Toughness of Irradiated Beryllium
    Beeston J.

    Irradiation Creep and Growth in Zirconium During Proton Bombardment
    Faulkner D., McElroy R.

    Radiation Damage Effects in 16-MeV Proton and 14-MeV Neutron Irradiated Nickel and Niobium
    Bradley E., Jones R., Styris D.

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

    Radiation Damage Function Analysis
    Gold R., Lippincott E., McElroy W., Simons R.

    Solid-State Track Recorder Materials for Use in Light-Water-Reactor Pressure Vessel Surveillance Exposures
    Gold R., Roberts J., Ruddy F.

    Microstructure and Tensile Properties of Heavily Irradiated 1100-0 Aluminum
    Farrell K., Richt A.

    Tensile Properties of Neutron-Irradiated 6061 Aluminum Alloy in Annealed and Precipitation-Hardened Conditions
    Farrell K., King R.

    Tensile Property Correlations for Highly Irradiated 20 Percent Cold-Worked Type 316 Stainless Steel
    Cannon N., Fish R., Wire G.

    Low-Cycle Fatigue of Three Irradiated and Unirradiated Vanstar Alloys
    Korth G., Schmunk R.

    Effects of Neutron Irradiation and Fatigue on Ductility of Stainless Steel DIN 1.4948
    de Vries M., Elej L., Staal H., van der Schaaf B.

    Estimates of Time-Dependent Fatigue Behavior of Type 316 Stainless Steel Subject to Irradiation Damage in Fast Breeder and Fusion Power Reactor Systems
    Brinkman C., Grossbeck M., Liu K.

    Fracture Toughness of Irradiated AISI 304 and 316L Stainless Steels
    Dufresne J., Henry B., Larsson H.

    Fracture Toughness of Irradiated Nimonic PE16 at High Temperatures
    Jones R., Nicholson R.

    Effects of Irradiation on the Mechanical Properties of Austenitic Stainless Steels Under Dynamic Loading
    Albertini C., Del Grande A., Montagnani M.

    Effects of Irradiation Temperature, Fluence, and Heating Rate on Postirradiation Flow Properties of Cladding Under Simulated Temperature Transient Heating and Deformation Conditions
    Cannon N., Duncan D.

    Effects of Irradiation Creep on Ex-Reactor Mechanical Properties
    Duncan D.

    Formulation of Constitutive Laws for Deformation During Irradiation
    Wolfer W.

    Irradiation Creep in Bending of Cold-Worked AISI 316 Stainless Steel at Low Neutron Fluence
    Appleby W., Marshall J., McSherry A., Patel M.

    A Comparison of Fuel Pin Deformations with Pressurized Tube Creep Tests
    Gilbert E., Lovell A., Taylor J.

    Reduction of Irradiation-Induced Creep by Point-Defect Trapping
    Mansur L., Wolfer W.

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

    In-Reactor Deformation and Fracture of Austenitic Stainless Steels
    Bloom E., Wolfer W.

    Index


    Committee: E10

    Paper ID: STP683-EB

    DOI: 10.1520/STP683-EB

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

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

    ASTM International is a member of CrossRef.

    0-8031-0327-1
    978-0-8031-0327-6
    STP683-EB