You are being redirected because this document is part of your ASTM Compass® subscription.
    This document is part of your ASTM Compass® subscription.


    Effects of Radiation on Materials: 20th International Symposium

    Rosinski ST, Grossbeck ML, Allen TR, Kumar AS
    Published: 2001

      Format Pages Price  
    PDF (18M) $234   ADD TO CART
    Hardcopy (shipping and handling) $234   ADD TO CART
    Hardcopy + PDF Bundle - Save 25%
    (shipping and handling)
    $351.00   ADD TO CART

    Fifty-seven papers provide a diverse and highly technical discussion of the influence of radiation on the microstructure and mechanical properties of structural materials. Nine sections cover: reactor pressure vessel (RPV) steels, austenitic and ferritic/martensitic alloys, proton and spallation neutron sources, radiation damage fundamentals, and other materials.

    Twenty-five papers discuss various aspects of radiation effects on RPV plate, forging, and weld materials, including radiation-induced changes on mechanical properties, radiation damage mechanisms and associated microstructural changes and the modeling of radiation embrittlement mechanisms.

    Eight papers discuss radiation-induced segregation, creep, irradiation-creep, swelling, and the associated changes in mechanical properties. Four papers discuss ferritic/martensitic alloys; and six papers examine the effects of high energy proton and spallation neutrons on the mechanical properties and corrosion behavior of various structural alloys. Finally, radiation damage fundamentals is the subject of four papers and the publication concludes with 10 papers covering a broad range of materials including vanadium alloys, tungsten rods, silicon film, silicon carbide and silicon carbide composites, shape-memory alloys, zirconium-niobium pressure tube materials, and other metals and alloys.

    Table of Contents

    Review of Current Recommendations from the Recent IAEA Specialists Meeting on Irradiation Effects on Pressure Vessel Steels and its Mitigation

    A Mechanistically-Based Model of Irradiation Damage in Low Alloy Steel Submerged Arc Welds

    Vessel Investigation Program of “CHOOZ A” PWR Reactor after Shutdown

    Development of Reconstitution Technology for Surveillance Specimens in Japan Power Engineering and Inspection Corporation

    Master Curve Characterization of Irradiation Embrittlement Using Standard and 1/3-Sized Precracked Charpy Specimens

    Radiation Damage Assessment by the Use of Dynamic Toughness Measurements on Pre-Cracked Charpy-V Specimens

    Comparison of Transition Temperature Shifts Between Static Fracture Toughness and Charpy-v Impact Properties Due to Irradiation and Post-Irradiation Annealing for Japanese A533B-1 Steels

    Yield and Toughness Transition Predictions for Irradiated Steels Based on Dislocation Mechanics

    Master Curve Evaluation of Irradiated Russian VVER Type Reactor Pressure Vessel Steels

    Fracture Toughness Characterization of 304L and 316L Austenitic Stainless Steels and Alloy 718 After Irradiation in High-Energy, Mixed Proton/Neutron Spectrum

    Review of Phosphorus Segregation and Intergranular Embrittlement in Reactor Pressure Vessel Steels

    Modeling of Phosphorus Accumulation on Grain Boundaries in Iron Alloys under Irradiation

    Grain Boundary Phosphorus Segregation Under Irradiation and Thermal Aging and Its Effect on the Ductile-to-Brittle Transition

    An Evaluation of Through-Thickness Changes in Primary Damage Production in Commercial Reactor Pressure Vessels

    Hardness and Microstructure Changes with Thermal Annealing of Neutron-Irradiated Fe-Cu Alloys

    Effects of Copper Concentration and Neutron Flux on Irradiation Hardening and Microstructure Evolution in Fe-Cu Model Alloys

    Effects of Neutron Irradiation and Thermal Annealing on Model Alloys Using Positron Annihilation Techniques

    Microstructural Evolution in High Nickel Submerged Arc Welds

    An Evaluation of the Effect of Radiation Environment on Linde 80 Reactor Vessel Welds

    Reirradiation Response Rate of a High-Copper Reactor Pressure Vessel Weld

    Relation Between Resistivity and Mechanical Properties in Heat Affected Zone of Welded Pressure Vessel Steel

    Fracture Toughness and Tensile Properties of Irradiated Reactor Pressure Vessel Cladding Material

    True Characteristics of Strength and Ductility for Neutron-Irradiated Metals and Alloys

    Investigation of Temper Embrittlement in Reactor Pressure Vessel Steels Following Thermal Aging, Irradiation, and Thermal Annealing

    Composition Effects on the Radiation Embrittlement of Iron Alloys

    The Determination of Bias Factor Stress Dependence from Experimental Data on Irradiation Creep and Stress-Affected Swelling in Austenitic Stainless Steels

    Swelling and Microstructural Evolution in 316 Stainless Steel Hexagonal Ducts Following Long-Term Irradiation in EBR-II

    Radiation-Induced Segregation and Void Swelling in 304 Stainless Steel

    Effect of Irradiation Environment of Fast Reactor's Fuel Elements on Void Swelling in P, Ti-Modified 316 Stainless Steel

    The Swelling Dependence of Cold Worked 16Cr-15Ni-2Mo-lMn Steel on Neutron Irradiation Temperature, Fluence and Damage Rate During Its Use as a Cladding Material in the BN-600 Reactor

    Tensile Properties of 12% Cold-Worked Type 316 Stainless Steel Irradiated in EBR-II Under Lower-Dose-Rate Conditions to High Fluence

    Irradiation Creep Deformation of Modified 316 and 15Cr-20Ni Base Austenitic Fuel Elements Irradiated in FFTF

    Behavior of Different Austenitic Stainless Steels, Conventional, Reduced Activation (RA) and ODS Chromium-Rich Ferritic-Martensitic Steels Under Neutron Irradiation at 325°C in PWR Environment

    Post-Irradiation Deformation Microstructures in Fe-9Cr

    Effect of Specimen Size on Fatigue Properties of Reduced Activation Ferritic/Martensitic Steel

    Correlation Between Creep Properties and Microstructure of Reduced Activation Ferritic/Martensitic Steels

    Comparison of Thermal Creep and Irradiation Creep of HT9 Pressurized Tubes at Test Temperatures from ∼490°C to 605°C

    Examination of 304L Stainless Steel to 6061-T6 Aluminum Inertia Welded Transition Joints after Irradiation in a Spallation Neutron Spectrum

    Microstructural Alteration of Structural Alloys by Low Temperature Irradiation with High Energy Protons and Spallation Neutrons

    Retention of Very High Levels of Helium and Hydrogen Generated in Various Structural Alloys by 800 MeV Protons and Spallation Neutrons

    The Influence of High Energy Proton Irradiation on the Corrosion of Materials

    The Effect of High Energy Protons and Neutrons on the Tensile Properties of Materials Selected for the Target and Blanket Components in the Accelerator Production of Tritium Project

    High-Energy Spallation Neutron Effects on the Tensile Properties of Materials for the Target and Blanket Components for the Accelerator Production of Tritium Project

    Microstructural Evolution of Reduced Activation and Conventional Martensitic Steels after Thermal Aging and Neutron Irradiation

    Dimensional Characteristics of Displacement Cascades in Austenitic Steels under Neutron Irradiation at Cryogenic Temperature

    On the α+γ↔γ-Phase Boundary in Nickel and in Manganese Containing Stainless Steel Alloys

    Effect of Nickel on Irradiation Hardening and Microstructure Evolution of Proton Irradiated Fe-Cu Alloys

    Effect of Final Irradiation Temperature and Frequency of Irradiation Temperature Cycles on Microstructural Evolution of Vanadium Alloys

    Hardening of Vanadium Doped with Nitrogen by Heavy Ion Irradiation and Post-Irradiation Annealing

    Hydrogen and Helium Gas Formation and their Release Kinetics in Tungsten Rods after Irradiation with 800 MeV Protons

    The Influence of Temperature, Fluence, Dose Rate, and Helium Production on Defect Accumulation and Swelling in Silicon Carbide

    Microstructural Stability of SiC/SiC Composites under Dual-Beam Ion Irradiation

    Molecular Dynamics Simulation of Radiation Damage Production in Cubic Silicon Carbide

    Influence of the Reactor and Cyclotron Irradiation on Energy Transformation during Plastic Deformation of Metal Materials

    Irradiation-Induced Amorphization and Its Recovery Behavior in Cold-Rolled and Aged Ti-Ni Shape Memory Alloys

    Effect of Mass and Energy on Preferential Amorphization in Polycrystalline Silicon Film during Ion Irradiation

    Crack Growth Resistance of Irradiated Zr-2.5Nb Pressure Tube Material at Low Hydrogen Levels

    Author Index

    Subject Index

    Committee: E10

    DOI: 10.1520/STP1405-EB

    ISBN-EB: 978-0-8031-5454-4

    ISBN-13: 978-0-8031-2878-1

    ASTM International is a member of CrossRef.