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    STP956

    Influence of Radiation on Material Properties: 13th International Symposium (Part II)

    Garner FA, Henager CH, Igata N
    Published: 1987


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    STP 956 includes: irradiation creep and creep rupture; changes in mechanical properties of alloys; pressure vessel steels; radiation damage in nonmetals; irradiation facilities; and dosimetry of radiation environments.


    Table of Contents

    Overview

    Radiation-Induced Creep of Aluminum and Copper

    Cessation of Irradiation Creep in AISI 316 Concurrent with High Levels of Swelling

    In-Reactor Creep Rupture Behavior of the D19 and 316 Alloys

    Analysis of the In-Reactor Creep and Rupture Life Behavior of Stabilized Austenitic Stainless Steels and the Nickel-Base Alloy Hastelloy-X

    In-Reactor Deformation of Zr-2.5 wt% Nb Pressure Tubes

    Light-Ion Irradiation Creep and Hardening of Model Ferritic Alloys

    The Ductile-to-Brittle Transition Behavior of Martensitic Steels Neutron Irradiated to 26 dpa

    Effects of Microstructure and Thermal Aging on Neutron Irradiation Embrittlement of 2¼Cr-1Mo Steel for a Nuclear Pressure Vessel

    Effects of 14-MeV Neutron Irradiations on Mechanical Properties of Ferritic Steels

    Impurity Element Effects on the Toughness of 12 Cr-1 Mo Steel

    Tensile Properties of Several 800 MeV Proton-Irradiated bcc Metals and Alloys

    Post-Irradiation Fracture Properties of Precipitation-Strengthened Alloy D21

    Mechanical Properties at Low and High Strain Rates of PE 16 Alloys Irradiated to 9.2 dpa

    J-Integral Toughness of Low Fluence Neutron-Irradiated Stainless Steel DIN 1.4948

    Fatigue Crack Growth and Fracture Toughness Properties of Low Fluence Neutron-Irradiated Type 316 and Type 304 Stainless Steels

    Experimental Assessments of Notch Ductility and Tensile Strength of Stainless Steel Weldments After 120°C Neutron Irradiation

    Effect of Cold Work on Tensile Behavior of Irradiated Type 316 Stainless Steel

    Radiation Effects on the Micromechanics of Fatigue Crack Initiation

    Hydrogen Buildup in Irradiated Type-304 Stainless Steel

    Mechanical Properties and Fracture Behavior of 20% Cold-Worked 316 Stainless Steel Irradiated to Very High Neutron Exposures

    The Effect of Neutron Irradiation on the Tensile Properties and Microstructure of Several Vanadium Alloys

    Tensile and Fracture Properties of EBR-II-Irradiated V-15Cr-5Ti Containing Helium

    The Effects of Temperature and Strain Rate on the Properties of (Fe,Ni)3V LRO Alloys

    Microstructural Characterization of Submerged Arc Weld Metals

    Comparison of Irradiation-Induced Transition Temperature Increases from Notch Ductility and Fracture Toughness Tests

    Comparison of the Effect of Power and Test Reactor Irradiations on the Fracture Properties of Submerged-Arc Welds

    Investigation of Neutron Irradiated Reactor Pressure Vessel Steel by Positron Annihilation and Electron Microscopy

    Tensile Properties of Irradiated Pressure Vessel Steels

    Effect of Interstitial Impurities on Fracture Characteristics of A533-B Class 1 Pressure Vessel Steel

    Irradiation Embrittlement of Advanced Pressure Vessel Steels

    A Comparison Between French Surveillance Program Results and Predictions of Irradiation Embrittlement

    The Effect of Thermal Annealing on the Fracture Properties of a Submerged-Arc Weld Metal

    Steel Impurity Element Effects on Postirradiation Properties Recovery by Annealing

    A Study of Radiation Induced Voids and Precipitates and Their Annealing Behavior by Small-Angle Neutron Scattering

    Irradiation Embrittlement Evaluation Without Lateral Expansion Measurements

    Trend Curve Data Development and Testing

    Damage Rate and Spectrum Effects in Ferritic Steel ΔNDTT Data

    Current Limitations of Trend Curve Analysis for the Prediction of Reactor PV Embrittlement

    A Statistical Analysis of Fracture Toughness of Irradiated Low-Alloy Steel Plate and Welds

    Fission Fragment Damage in Ceramic Nuclear Fuels

    Fission Fragment Induced Hardening in Uranium Mononitride

    The Assessment of Seal Performance and Lifetime Prediction in a Nuclear Environment

    The Effects of Radiation on Organic Matrix Waste Forms

    Hydrogen Control in the Handling, Shipping, and Storage of Wet Radioactive Waste

    Photobleaching Effects on Radiation-Induced Loss for Silica Glass Image Fiber

    Irradiation Devices for Reactor Materials: Results Obtained from Irradiated Lithium Aluminate at the OSIRIS Reactor

    Irradiation Effects in KAPTON Polyimide Film from 14-MeV Neutrons and Cobalt-60 Gamma Rays

    Changes in Surface Morphology and Microcrack Initiation in Polymers Under Simultaneous Exposure to Stress and Fast Atom Bombardment

    Effect of Gamma Radiation on the Permeability of Opthalmic Preservatives Through Fluorine Surface-Treated Low-Density Polyethylene Bottles

    The Low-Temperature Neutron Irradiation Facility at ORNL

    Irradiation Facilities at the Idaho National Engineering Laboratory

    Operating Experience at the Los Alamos Spallation Radiation Effects Facility at LAMPF

    Additional Measurements of the Radiation Environment at the Los Alamos Spallation Radiation Effects Facility at LAMPF

    Recent Research in Neutron Dosimetry and Damage Analysis for Materials Irradiations

    Improvement of Accuracy Assessment in Radiation Damage Predictions

    Comparison of Calculated Integral Values Using Measured and Calculated Neutron Spectra for Fusion Neutronics Analyses

    Measurements of 10B(n,He) Reaction Rates in a Mockup Control Rod in ZPPR

    Spectrum Integrated (n,He) Cross Section Comparison and Least Squares Analysis for 6Li and 10B in Benchmark Fields

    Author Index

    Subject Index


    Committee: E10

    DOI: 10.1520/STP956-EB

    ISBN-EB: 978-0-8031-5017-1

    ISBN-13: 978-0-8031-0963-6

    ASTM International is a member of CrossRef.

    0-8031-0963-6
    978-0-8031-0963-6
    STP956-EB