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    STP870

    Effects of Radiation on Materials: Twelfth International Symposium

    Garner FA, Perrin JS
    Published: 1985


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    Two volumes present recent research on radiation damage to structural materials in both fission and fusion environments. Seventy papers discuss: irradiation creep of structural metals; microstructural development; neutron-induced swelling; charge particle irradiation; theory of swelling; mechanical properties; pressure vessel steels; irradiation facilities; and other radiation studies.


    Table of Contents

    Overview

    In-Reactor Creep of Selected Ferritic Alloys

    Evaluation of Ferritic Alloy Fe-2¼Cr-1Mo After Neutron Irradiation: Irradiation Creep and Swelling

    Influence of a Temperature Change on In-Reactor Creep

    Non-Isothermal In-Reactor Creep of Nickel Alloys Inconel 706 and PE-16

    In-Pile Creep Strain and Failure of Cold-Worked Type 316 Titanium Pressurized Tubes

    Critical Assessment of Low-Fluence Irradiation Creep Mechanisms

    Irradiation-Creep-Induced Anisotropy in a/2 <110> Dislocation Populations

    Effect of Irradiation Temperature on the Precipitation in Cold-Worked Titanium-Stabilized Type 316 Stainless Steel

    Microstructure of Irradiated Inconel 706 Fuel Pin Cladding

    Microsegregation Observed in Fe-35.5Ni-7.5Cr Irradiated in EBR-II

    Transmission Electron Microscope Studies and Microhardness Testing of Irradiated Ferritic Steels

    Phase Stability in Irradiated Alloys by Constrained Equilibrium Thermodynamics

    Swelling of Austenitic Iron-Nickel-Chromium Ternary Alloys During Fast Neutron Irradiation

    Swelling of 20% Cold-Worked Type 316 Stainless Steel Fuel Pin Cladding and Ducts

    Swelling of AISI Type 304L Stainless Steel in Response to Simultaneous Variations in Stress and Displacement Rate

    Some Observations on the Effect of Stress on Irradiation-Induced Swelling in AISI Type 316 Stainless Steel

    Swelling of Microstructure of Neutron-Irradiated Titanium-Modified Type 316 Stainless Steel

    Role of Dislocations, Dislocation Walls, and Grain Boundaries in Void Formation During Early Stages of Fast Neutron Irradiation

    Influence of Applied Stress on Swelling Behavior in Type 304 Stainless Steel

    Evolution of Cavity Microstructure in Ion-Irradiated Type 316 Stainless Steel and Fe-20Ni-15Cr Alloy

    Experimental Investigation of the Effect of Injected Interstitials on Void Formation

    Influence of Helium on Swelling of Steels

    Comparison of Depth-Dependent Microstructures of Ion-Irradiated Type 316 Stainless Steels

    Experimental Determination of the Critical Cavity Radius in Fe-10Cr for Ion Irradiation

    Comparison of Thermal and Irradiated Behavior of High-Strength, High-Conductivity Copper Alloys

    Ion Bombardment Damage in a Modified Fe-9Cr-1Mo Steel

    Helium and Displacement Damage Produced by 600 MeV Proton Beams in High Purity Aluminum

    Direct Observation of Cascade Defect Formation at Low Temperatures in Ion-Irradiated Metals

    Solute Segregation and Void Formation on Grain Boundaries in Electron-Irradiated Type 316 Stainless Steel

    Nonequilibrium Segregation and Phase Instability in Alloy Films During Elevated-Temperature Irradiation in a High-Voltage Electron Microscope

    Modeling of Void Swelling in Irradiated Steels

    Influence of Composition on Steady-State Void Nucleation in Irradiated Alloys

    Effect of Microstructure on the Minimum Critical Radius and Critical Number of Gas Atoms for Swelling

    Dual-Ion Irradiation: Impact of the Conflicting Roles of Helium on Void Nucleation

    Nucleation of Voids—The Impurity Effect

    A Mechanism of Void Lattice Formation Based on Two-Dimensional Self-Interstitial Diffusion


    Committee: E10

    DOI: 10.1520/STP870-EB

    ISBN-EB: 978-0-8031-4935-9

    ISBN-13: 978-0-8031-0450-1

    ASTM International is a member of CrossRef.

    0-8031-0450-2
    978-0-8031-0450-1
    STP870-EB