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    STP1046V2

    Effects of Radiation on Materials: 14th International Symposium (Volume II)

    Packan Nicolas, Stoller Roger, Kumar Arvind
    Published: 1990


      Format Pages Price  



    Table of Contents

    Overview

    Effects of 50°C Surveillance and Test Reactor Irradiations on Ferritic Pressure Vessel Steel Embrittlement

    Application of a United Kingdom Magnox Steel Irradiation Model to the HFIR Pressure Vessel

    Tensile Properties of Neutron Irradiated A212B Pressure Vessel Steel

    Experimental Assessments of Gundremmingen RPV Archival Material for Fluence Rate Effects Studies

    Investigation of Materials from a Decommissioned Reactor Pressure Vessel—A Contribution to the Understanding of Irradiation Embrittlement

    Fine-Scale Microstructural Characterization of Pressure Vessel Steels and Related Materials Using APFIM

    An Analysis of Small Clusters Formed in Thermally Aged and Irradiated FeCu and FeCuNi Model Alloys

    SANS and DENS Study of Irradiation Damage in a Reactor Pressure Vessel Material with a Systematic Variation of Irradiation Dose and Heat Treatments

    Magnetoacoustic and Barkhausen Emission Studies of Neutron Irradiated Iron and Iron-Copper Alloys

    Precipitation in an Aged Fe-0.85 at%Cu Alloy Observed by Muon Spin Rotation Spectroscopy: A Prospective Method of Studying Irradiation Hardening

    An Evaluation of Linde 80 Submerged-Arc Weld Metal Charpy Data Irradiated in the HSST Program

    Effects of Radiation on KIc Curves for High Copper Welds

    Improved Correlations for Predicting the Effects of Neutron Radiation on Linde 80 Submerged-Arc Weld Metals

    Fracture Toughness Shifts and Bounds for Irradiated Reactor Pressure Vessel Materials

    Comparison of Experimental 41 J Shifts with the Predictions of German KTA 3203 and U.S. NRC Regulatory Guide 1.99

    The Nil-Ductility Temperature Shift Arising from Irradiation as Predicted Through the French Test Reactor Experiments

    The Effects of Mechanical Stress Gradients on Irradiation-Induced Embrittlement of Pressure Vessel Steel

    The Effect of Nickel on Irradiation Hardening of Pressure Vessel Steels

    Fracture Resistance of Irradiated Stainless Steel Clad Vessels

    Tensile and Charpy Impact Behavior of an Irradiated Three-Wire Series-Arc Stainless Steel Cladding

    Correlation of Cv and Drop-Weight Transition Temperature Increase Caused by Irradiation

    Residual Tensile Properties at Low and High Strain Rates of AISI 316H Predamaged by Creep, Low Cycle Fatigue, and Irradiation to 2 dpa

    Response of Ferritic/Martensitic Steels to Neutrons at Irradiation Temperatures from 20 to 823 K

    Serrated Flow in Irradiated and Partially Denitrided Mild Steel

    Effects of High Thermal and High Fast Fluences on the Mechanical Properties of Type 6061 Aluminum on the HFBR

    Charpy Impact Test Results of Ferritic Alloys Irradiated to 10 dpa at 55°C

    Fracture Behavior of Ferritic Steels Irradiated at 50°C in the High-Flux Isotope Reactor (HFIR)

    Evaluation of the Fracture Toughness of Irradiated Stainless Steel Using Short Rod Specimens

    Effect of Specimen Size on the Upper Shelf Energy of Ferritic Steels

    Evaluation of Irradiation Embrittlement by Instrumented Impact Testing

    Evaluation of Ring Tensile Test Results—A Semiempirical Approach

    Irradiation Creep Behavior of the Fusion Heats of HT9 and Modified 9Cr-1 Mo Steels

    Irradiation Creep in Austenitic Stainless Steels at 60 to 400°C with a Fusion Reactor Helium to dpa Ratio

    Influence of Thermomechanical Treatment and Environmental History on Creep, Swelling, and Embrittlement of AISI 316 at 400°Cand 130 dpa

    Swelling and In-Pile Creep Behavior of Some 15Cr15NiTi Stainless Steels in the Temperature Range 400 to 600°C

    The Cantilever Beam Method for Simulating Irradiation Creep and Growth

    Effects of Neutron Irradiation to 98 dpa on the Swelling of Various Copper Alloys

    EURAC: A Concept for a European Accelerator Neutron Source

    Analysis of Transmutation Nuclide Production in a Spallation Neutron Source

    Radiation Damage Calculations for Compound Materials

    Neutron Spectra Calculations for Ex-Core Irradiation Experiments at the Buffalo Reactor

    Consideration of Calculated and Experimental Neutron Dosimetry for Out-of-Core Metallurgy Irradiation Experiments at the Buffalo Reactor

    Neutron-Induced Swelling of Commercial Alloys at Very High Exposures

    Effect of Neutron Radiation on Mechanical Properties of Permanent Near Core Structures

    Influence of Swelling on Irradiated CW Titanium Modified 316 Embrittlement

    The Influence of Creep Damage and Neutron Irradiation on the Tensile Properties of Type 304 Stainless Steel

    Simulated Transient Behavior of HT9 Cladding

    The Swelling Behavior of Titanium-Stabilized Austenitic Steels Used as Structural Materials of Fissile Subassemblies in Phénix

    Irradiation Creep and Swelling of OX16H15M3B Steel and Its Modification 0X16H15M3BP Steel

    Operational Behavior of FBR Mixed Oxide Fuel Pins

    In Situ High Voltage Electron Microscopy Investigation of Catastrophic Swelling in Uranium Intermetallic Fuels

    The Effect of Crystal Structure Stability on Swelling in Intermetallic Uranium Compounds

    Author Index

    Subject Index


    Committee: E10

    DOI: 10.1520/STP1046V2-EB

    ISBN-EB: 978-0-8031-8887-7

    ISBN-13: 978-0-8031-1266-7

    ASTM International is a member of CrossRef.

    0-8031-1266-1
    978-0-8031-1266-7
    STP1046V2-EB