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    Effects of Radiation on Materials: 17th International Symposium

    Gelles DS, Nanstad RK, Kumar AS, Little EA
    Published: 1996

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    STP 1270 features the latest information from the world's leading experts on how radiation impacts a wide range of metals. This extensive volume includes 68 peer-reviewed papers organized into 8 comprehensive categories:

    Modeling of Controlling Mechanisms -- 8 papers explore mechanisms controlling the behavior and process of radiation embrittlement and segregation in reactor pressure vessel steel.

    MicrostructureStudies -- The precipitation process that controls reactor pressure vessel steel embrittlement is discussed in 6 papers.

    Charpy Impact Response -- 14 papers explore such properties topics as the effects of annealing, irradiated welds and specific reactor parts, consequences of flux, and the use of small specimen technology and reconstitution.

    Strength and Toughness Issues -- 11 papers expand the mechanical properties data base on reactor pressure vessel steels.

    Ferritic and Martensitic Steels -- Steels with increased chromium levels for use at higher temperature are examined in 6 papers.

    Austenitic Steels -- 12 papers present topics including microstructural response, fundamentals of radiation damage and mechanical properties.

    Other Materials -- Nickel, aluminum alloys, vanadium and a zirconium alloy are the focus of 7 papers.

    Special Procedures and Techniques -- 4 papers feature procedures for avoiding long term radioactivity and unique methods such as positron measurements and laser extensometry.

    Table of Contents

    Mechanisms Controlling the Composition Influence on Radiation Hardening and Embrittlement of Iron-Base Alloys

    Pressure Vessel Embrittlement Predictions Based on a Composite Model of Copper Precipitation and Point Defect Clustering

    The B&W Owners Group Program for Microstructural Characterization and Radiation Embrittlement Modelling of Linde 80 Reactor Vessel Welds

    Irradiation Embrittlement Modelling of Linde 80 Weld Metals

    Modeling of Irradiation Embrittlement and Annealing/Recovery in Pressure Vessel Steels

    The Modelling of Irradiation Embrittlement in Submerged-Arc Welds

    The Modelling of Irradiation-Enhanced Phosphorus Segregation in Neutron Irradiated Reactor Pressure Vessel Submerged-Arc Welds

    Research to Understand the Embrittlement Behavior of Yankee/BR3 Surveillance Plate and Other Outlier RPV Steels

    Electron Microscopy and Small Angle Neutron Scattering Study of Precipitation in Low Alloy Steel Submerged-Arc Welds

    Radiation Damage Studies Using Small-Angle Neutron Scattering

    Damage Structures of Proton Irradiated Fe-0.3wt.%Cu Alloy

    Mitigation of Irradiation Embrittlement by Annealing

    Microstructure and Mechanical Properties of WWER-440 Reactor Vessel Metal After Service Life Expiration and Recovery Anneal

    A Microstructural Study of Phosphorus Segregation and Intergranular Fracture in Neutron Irradiated Submerged-Arc Welds

    Effects of Annealing Time on the Recovery of Charpy V-Notch Properties of Irradiated High-Ccopper Weld Metal

    In-Service Embrittlement of the Pressure Vessel Welds at the Doel I And II Nuclear Power Plants

    The Toughness of Irradiated Pressure Water Reactor (PWR) Vessel Shell Rings and the Effect of Segregation Zones

    Low Temperature Embrittlement of RPV Support Structure Steel

    Effects of Neutron Flux and Irradiation Temperature on Irradiation Embrittlement of A533B Steels

    The Interpretation of Charpy Impact Test Data Using Hyper-Logistic Fitting Functions

    Uncertainty Evaluation in Transition Temperature Measurements

    On Impact Testing of Subsize Charpy V-Notch Type Specimens

    Reconstitution: Where Do We Stand?

    The Reconstitution of Charpy-Size Tensile Specimens

    Notch Reorientation of Charpy-V Specimens of the BWR Philippsburg 1 Through Reconstitution

    Variations in Charpy Impact Data Evaluated by a Round-Robin Testing Program — A Summary

    The Embrittlement Data Base (EDB) and Its Applications

    Surveillance Programme for WWER-440/Type 213 Reactor Pressure Vessels- Standard Programme, Re-Evaluation of Results, Supplementary Programme

    Application of Micromechanical Models of Ductile Fracture Initiation to Reactor Pressure Vessel Materials

    On the Effect of Flux and Composition on Irradiation Hardening at 60°C

    The Dependence of Radiation Hardening and Embrittlement on Irradiation Temperature

    HFIR Steels Embrittlement: The Possible Effect of Gamma Field Contribution

    The Influence of Metallurgical Variables on the Temperature Dependence of Irradiation Hardening in Pressure Vessel Steels

    Effects of Proton Irradiation on Positron Annihilation and Micro-Vickers Hardness of Fe-C-Cu Model Alloys

    Ductile Fracture Mechanisms in an A302B Modified Reactor Pressure Vessel Steel

    Fracture Toughness Test Results of Thermal Aged Reactor Vessel Materials

    The Effect of Constraint on Toughness of a Pressure Vessel Steel

    The Effects of Thermal Annealing on Fracture Toughness of Low Upper-Shelf Welds

    Evaluation of Embrittlement in a Pressure Vessel Steel by Fracture Reconstruction

    The Microstructural Stability and Mechanical Properties of Two Low Activation Martensitic Steels

    Influence of Thermomechanical Treatment on Irradiation Microstructures in an ODS Ferritic Steel

    Effect of Boron on Post Irradiation Tensile Properties of Reduced Activation Ferritic Steel (F-82H) Irradiated in HFIR

    Irradiation Effects on Base Metal and Welds of 9Cr-1Mo (EM10) Martensitic Steel

    Evaluation of the Upper Shelf Energy for Ferritic Steels from Miniaturized Charpy Specimen Data

    On the Role of Strain Rate, Size and Notch Acuity on Toughness: A Comparison of Two Martensitic Stainless Steels

    Microstructural Evolution of Austenitic Stainless Steels Irradiated in a Fast Reactor

    Effects of Helium/DPA Ratio, Alloy Composition and Cold Work on Microstructural Evolution and Hardening of 59Ni-Doped Fe-Cr-Ni Alloys Neutron-Irradiated at 465°C

    Swelling, Mechanical Properties and Structure of Austenitic High-Nickel Alloy Irradiated in a Fast Reactor

    Effects of Metallurgical Variables on Swelling of Modified 316 and Higher Ni Austenitic Stainless Steels

    On the Fundamentals of Radiation Damage in FCC Materials, A Review

    An Investigation of Microstructures and Yield Strengths in Irradiated Austenitic Stainless Steels Using Small Specimen Techniques

    Irradiation Hardening and Loss of Ductility of Type 316L(N) Stainless Steel Plate Material Due to Neutron-Irradiation

    Fatigue Crack Propagation by Channel Fracture in Irradiated 316 Stainless Steel

    Fracture Toughness of Irradiated Candidate Materials for ITER First Wall/Blanket Structures

    Irradiation Behavior of Weldments of Austenitic Stainless Steel Made by Various Welding Techniques

    Helium Effects on the Reweldability and Low Cycle Fatigue Properties of Welded Joints for Type Cr16Ni11Mo3Ti and 316L(N) Stainless Steels

    Data Collection on the Effect of Irradiation on the Mechanical Properties of Austenitic Stainless Steels and Weld Metals

    Bubble Microstructure Evolution and Helium Behavior in He+ Implanted Ni-Base Alloys

    Saturation of Swelling in Neutron Irradiated Pure Nickel and Its Dependence on Temperature and Starting Dislocation Microstructure

    Effect of Irradiation in a Spallation Neutron Environment on Tensile Properties and Microstructure of Aluminum Alloys 5052 and 6061

    Correlation Between Shear Punch and Tensile Data for Neutron-Irradiated Aluminum Alloys

    Effect of Dynamically Charged Helium on Mechanical Properties of Vanadium-Base Alloys

    Swelling and Structure of Vanadium-Base Alloys Irradiated in the Dynamic Helium Charging Experiment

    Corrosion Response of Pre-Irradiated Zr-2.5Nb Pressure Tube Material

    The Development of Structural Materials for Reduced Long-Term Activation

    Characterization of Irradiation-Induced Precipitates by Small Angle X-Ray and Neutron Scattering Experiments

    Variable Energy Positron Measurements at Nitrogen Ion Bombarded Steel Surfaces

    Use of Laser Extensometer for Mechanical Tests on Irradiated Materials

    Committee: E10

    DOI: 10.1520/STP1270-EB

    ISBN-EB: 978-0-8031-5328-8

    ISBN-13: 978-0-8031-2016-7