STP725

    Effects of Radiation on Materials

    Kramer D, Brager HR, Perrin JS
    Published: 1981


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    Extensive information on current research results dealing with the effects of radiation on light-water-reactor pressure vessels, fast breeder reactor core materials, material for first-walls in fusion systems, and solid radioactive waste.


    Table of Contents

    Introduction

    Summary

    Apparent Embrittlement Saturation and Radiation Mechanisms of Reactor Pressure Vessel Steels

    Radiation Embrittlement of a PWR Vessel Steel: Effects of Impurities and Nickel Content

    Correlation Between Microhardness, Tensile Properties, and Notch Ductility of Irradiated Ferritic Steels

    Irradiation Surveillance Program as Applied in Switzerland

    Experimental Investigation of Multicycle Irradiation and Annealing Effects on Notch Ductility of A533-B Weld Deposits

    J-R Curve Characterization of A533-B Weld Metal with Irradiation and Postirradiation Annealing

    Influence of Neutron Irradiation on Mechanical Properties of Steels Under Impulsive Loading

    Fatigue Crack Growth Rates of Irradiated Pressure Vessel Steels in Simulated Nuclear Coolant Environment

    Significance of Radiation Effects in Solid Radioactive Waste

    An Internally Consistent Model for Radiation-Induced Void Swelling

    Radiation-Enhanced Diffusion in Face-Centered Cubic Materials

    Positron Lifetime Studies of Electron-Irradiated Copper

    Simulation of Short-Term Annealing of Displacement Cascades in Face-Centered Cubic Metals

    High-Density Equation of State for Helium and Its Application to Bubbles in Solids

    Applications of the Theory of Cavity Growth to Dual-Ion Swelling Experiments

    Ductility Loss of Ion-Irradiated Zircaloy-2 in Iodine Environment

    Radiation Hardening in Neutron-Irradiated Molybdenum and Its Alloys

    Fracture Resistance of HT-9 After Irradiation at Elevated Temperature

    Tensile, Creep, and Fatigue Properties of Low-Fluence Neutron-Irradiated Welded Joints DIN 1.4948

    Mechanical and Physical Properties of Irradiated Type 348 Stainless Steel

    Tensile Properties of Neutron-Irradiated Nimonic PE16

    Effects of Neutron Irradiation on Fatigue and Creep-Fatigue Crack Propagation in Type 316 Stainless Steel at 649°C

    State Variable Description of 316 Stainless Steel Postirradiation Mechanical Properties

    A Microstructural Interpretation of the Fluence and Temperature Dependence of the Mechanical Properties of Irradiated AISI 316

    Coarse Slip Processes and Crack Propagation in Irradiated Stainless Steel

    Dynamic Mechanical Properties of AISI 304L Irradiated to 2.2 dpa

    Postirradiation Cladding Strength Under Biaxial Loading with an Increasing Temperature Ramp

    Microstructural Development in Dual-Ion-Bombarded 316 Stainless Steel

    Microchemical Evolution of Neutron-Irradiated Stainless Steel

    Comparison of High-Fluence Swelling Behavior of Austenitic Stainless Steels

    Response to Annealing and Reirradiation of AISI 304L Stainless Steel Following Initial High-Dose Neutron Irradiation in EBR-II

    Point-Defect Clustering in the Presence of Mobile Helium and Immobile Traps

    Effects of Dose Rate on the Precipitate Distribution in an Ion-Irradiated Nickel-Aluminum Alloy

    Swelling in Reactor-Conditioned Nickel-Ion Irradiated Nimonic PE16

    Gamma Prime Coarsening and Redistribution in Nimonic PE16

    Effect of Material Variables on the Irradiation Performance of Boron Carbide

    A Microstructural Explanation for the Low Swelling of Ferritic Steels

    Irradiation-Induced Precipitation in Binary Palladium-Refractory Metal Alloys

    Void Swelling in Molybdenum Alloys In Situ Observed by a High-Voltage Electron Microscope

    A Study of Radiation Damage Produced in Thinned Specimens of 316 Stainless Steel by Energetic Helium Ions

    Helium Bubble Growth in Vanadium

    Irradiated Materials Measurement Technology

    Stress-Enhanced Swelling of Metals During Irradiation

    Effect of Temperature Changes on Swelling and Creep of AISI 316

    Reduction of Irradiation-Induced Creep and Swelling in AISI 316 by Compositional Modifications

    Frank Loop Formation in Irradiated Metals in Response to Applied and Internal Stresses

    Index


    Committee: E10

    DOI: 10.1520/STP725-EB

    ISBN-EB: 978-0-8031-4794-2

    ISBN-13: 978-0-8031-0755-7

    ASTM International is a member of CrossRef.

    0-8031-0755-2
    978-0-8031-0755-7
    STP725-EB