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    Effects of Radiation on Materials

    Brager HR, Perrin JS
    Published: 1982

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    This publication is divided into five major subject areas: Creep and Swelling; Microstructural Development; Pressure Vessel Steels; Mechanical Properties; Charged Particle Irradiation; Theory of Radiation Effects.

    Table of Contents


    The Swelling of Solution Annealed 316 Cladding in Rapsodie and Phenix

    The Swelling Behavior of 20% CW 316 Stainless Steel Cladding Irradiated With and Without Adjacent Fuel

    Interdependence of In-Pile Creep and Void Swelling in Ti- and Nb-Stabilized Stainless Steels

    Initial Results of Swelling and Irradiation Creep Interaction Testing

    Creep and Swelling of Type 348 Stainless Steel at Temperatures up to 700 K and Comparison with Fast Reactor Data

    Effect of Preinjected Helium on Swelling and Microstructure of Neutron Irradiated Pressurized Tubes of Type 316 Stainless Steel

    An In-Reactor Creep Correlation for 20% Cold Worked AISI 316 Stainless Steel

    Analysis of the High Fluence Creep Behavior of Two Precipitation Strengthened Alloys

    Microstructural Changes in Neutron-Irradiated Commercial Alloys: A Sequel

    The Influence of Cold Work Level, Solute and Helium Content on the Swelling of “Pure” AISI 316 (Fe-17Cr-16.7Ni-2.5Mo)

    Precipitation in Irradiated and Unirradiated Austenitic Steels

    Relationship Between Phase Development and Swelling of AISI 316 During Temperature Changes

    Microstructural Stability of Fast Reactor Irradiated 10–12%Cr Ferritic-Martensitic Stainless Steels

    Dislocation Substructure in Zirconium Alloys Irradiated in EBR-II

    The Effect of Preimplanted Helium on the Microstructure of Neutron Irradiated Nb, Nb-1%Zr and Nb-1%Zr-0.4%Mo

    Swelling in Neutron Irradiated Titanium Alloys

    The Effect of Helium on Swelling in Stainless Steel: Influence of Cavity Density and Morphology

    History Dependence and Consequences of the Microchemical Evolution of AISI 316

    Influence of Dose and Dose Rate Ont the Microstructure of Solution Annealed 316 Steel Irradiated Around 600 °C

    Microstructure and Tensile Properties of Neutron-Irradiated (Fe0.61Ni0.39)3V Ordered Alloy

    The Influence of Neutron Exposure, Chemical Composition and Metallurgical Condition, on the Irradiation Shift of Reactor Pressure Vessel Steels

    Significance of Nickel and Copper Content to Radiation Sensitivity and Postirradiation Heat Treatment Recovery of Reactor Vessel Steels

    Radiation Embrittlement of PWR Reactor Vessel Weld Metals : Nickel and Copper Synergism Effects

    Comparative Irradiation Study of Reactor Pressure-Vessel Steel Weld Metals

    Evaluation of Advanced Reactor Pressure Vessel Steels Under Neutron Irradiation

    Analysis of Fracture Surfaces of Reactor Pressure-Vessel Steels

    The Effect of Accelerated Irradiation on Fracture Behaviour

    Analytic Predictions of Embrittlement of SA 533 B Pressure Vessel Steels

    Kinetics of Annealing of Irradiated Surveillance Pressure Vessel Steel

    Irradiation Experiments in the Testing Nuclear Power Plant Vak

    Effects of Neutron Irradiation and Temperature on High Strain Rate Behaviour of Reactor Pressure Vessel Steel

    A Single Specimen Method for Determining Upper Shelf Fracture Toughness Shifts Using Precracked Charpy Specimens

    Preparation of Reconstituted Charpy V-Notch Impact Specimens for Generating Pressure Vessel Steel Fracture Toughness Data

    Low Dose Irradiation Effects of Heat-to-Heat Variation of Type 304 Stainless Steel Creep and Tensile Properties

    Irradiation Embrittlement in Some Austenitic Superalloys

    Mechanical Properties of Highly Irradiated 20 Percent Cold Worked Type 316 Stainless Steel

    Nickel-Doped Ferritic (Martensitic) Steels for Fusion Reactor Irradiation Studies: Tempering Behavior and Unirradiated and Irradiated Tensile Properties

    Effects of Temperature and Strain Rate on the Low Cycle Fatigue Properties of Neutron Irradiated Stainless Steel DIN 1.4948

    Deformation Microstructure Developed During Fatigue Crack Propagation in Type 316 Stainless Steel at 593°C

    Effects of Fast Neutron Irradiation on the Fracture Behavior of Stainless Steel

    Fatigue Crack Growth of Low-Fluence Neutron-Irradiated Stainless Steel DIN 1.4948

    The Influence of Neutron Irradiation on the Properties of Beryllium

    A Comparison of Transient-Heating Burst Test Results of Unirradiated and Irradiated Zircaloy-4 Fuel Rod Cladding

    Effects of Neutron Irradiation on the Mechanical Properties of a 5154-0 Type Aluminum Alloy

    On the Possibility of Using Amorphous Metals in High Radiation Environments

    Annealing of Radiation Damaged Monazite

    Void Swelling of Ferritic Alloys Bombarded with Nickel Ions

    Void Swelling and Phase Stability in Different Heats of Cold-Drawn Type 1.4970 Stainless Steel After Heavy-Ion Irradiation

    Irradiation Creep of Dilute Nickel Alloys

    Optimization of Precipitation Hardened Fe-Ni-Cr Alloys Using Nickel Ion Bombardment Simulation Studies

    Ion Damage in 316 Stainless Steel Over a Broad Dose Range

    Surface Segregation in Concentrated Ni-Cu Alloys Under Irradiation

    The Effect of Nitrogen on Void Swelling of Stainless Steel

    Mechanical Properties of 800-MeV Proton-Irradiated Metals2

    Damage Profile In Ion-Bombarded Nickel and Stainless Steel

    The Effect of Pulse Irradiation on Void Swelling of a “Pure” 316 Stainless Steel

    Comparison of Neutron and Heavy-Ion Damage in a Single-Phase Austenite

    Defect Production Rates by Electrons, Ions and Neutrons in Cubic Metals

    Kinetics of Radiation-Induced Segregation in Ternary Alloys

    Effect of Radiation-Induced Segregation on Void Nucleation

    On Radiation-Induced Segregation and the Compositional Dependence of Swelling in Fe-Ni-Cr Alloys

    Calculation of Cavity Nucleation Under Irradiation with Continuous Helium Generation

    Hardening of Irradiated Alloys due to the Simultaneous Formation of Vacancy and Interstitial Loops

    A Model for the Evolution of Network Dislocation Density in Irradiated Metals

    Asymmetric Dislocation/Point-Defect Interactions and the Modeling of Void Swelling

    Cooperative Effects in Microstructural Evolutions Under Irradiation: Fundamental Aspects

    Three Mile Island-2: Influence on Commercial Nuclear Power Development

    The European Fusion Materials Programme

    Fusion Materials Development in the U.S.

    Rapsodie and Phenix — The Materials Story

    The U.K. Fast Reactor Materials Programme


    Committee: E10

    DOI: 10.1520/STP782-EB

    ISBN-EB: 978-0-8031-4846-8

    ISBN-13: 978-0-8031-0753-3