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    STP611

    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

    Introduction

    Effects of Prior Stress History on Irradiation-Induced Creep

    Analysis of In-Reactor Stress Relaxation Using Irradiation Creep Models

    Dynamic Strain-Aging and Neutron Irradiation in Mild Steel

    Swelling and Tensile Property Changes in Neutron-Irradiated Type 316 Stainless Steel

    Effect of Fast Reactor Irradiation on the Tensile Properties of 20 Percent Cold-Worked Type 316 Stainless Steel

    Mechanical Properties of Fast Reactor Fuel Cladding for Transient Analysis

    Tensile Properties of Fast Reactor Irradiated Type 304 Stainless Steel

    Effects of Neutron Irradiation on Microstructure and Mechanical Properties of Nimonic PE-16

    Irradiation and Thermal Effects on the Tensile Properties of Inconel-718

    Tensile and Hardness Property Evaluations of Irradiated Zircaloy Cladding Under Off-Normal and Transient Conditions

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

    Swelling Simulation Studies of Type 316 Stainless Steel

    Development and Evaluation of a Stress-Free Swelling Correlation for 20 Percent Cold-Worked Type 316 Stainless Steel

    Swelling Behavior of Commercial Ferritic Alloys, EM-12 and HT-9, as Assessed by Heavy Ion Bombardment

    Observation of Defect Clusters of Columbium and Columbium Alloys In Situ Irradiated Under a High-Voltage Electron Microscope

    Void Growth Suppression by Dislocation Impurity Atmospheres

    Dependence of Void Swelling on the Electron Vacancy Concentration

    Microstructure and Mechanisms of Ion-Simulated Irradiation-Induced Creep of Nickel

    Effects of Interstitial Solutes on the Microstructures of Self-Ion Irradiated Vanadium

    Swelling and Gamma-Prime Particle Stability of Ion-Bombarded Iron-Chromium-Nickel Alloys

    Effect of Ion Irradiation on the Microstructure of an Iron-Nickel-Chromium Alloy

    Microstructural Changes in Ion-Irradiated Commercial Alloys

    Nickel-Ion Damage in a Precipitation-Hardened Nickel-Aluminum

    Fracture Mechanics Characterization of the Trino Reactor Vessel Material

    Evaluation of the Maine Yankee Reactor Beltline Materials

    Evaluation of the Effect of Chemical Composition on the Irradiation Sensitivity of Reactor Vessel Weld Metal

    Annealing of Irradiation Damage in High-Copper Ferritic Steels

    Displacement Spike Annealing in Iron at Reactor Temperatures

    Neutron Displacement Damage Cross Sections for Structural Metals

    Index


    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.

    0-8031-0388-3
    978-0-8031-0388-7
    STP611-EB