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    Effects of Radiation on Materials: 16th International Symposium

    Kumar AE, Gelles DS, Nanstad RK, Little TA
    Published: 1994

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    Comprehensive look at the latest research on how radiation effects metal and non-metal materials, with emphasis on fundamental mechanisms of damage and applications to nuclear systems.

    Over 80 peer-review papers in 15 sections. The diversity of the selections cover a complete range of topics, including:

    • The importance of research on radiation embrittlement as a predictor of safety margins

    • General aspects of radiation damage

    • Research covering reactor pressure vessels (RPV) steels and the various properties and microstructures

    • Results of studies of ferritic and ferritic-martensitic steels

    • Areas of research involving austentic alloys, copper and copper alloys, as well as alloys of zirconium, aluminum and vanadium

    • Irradiation of nonmetallics, including one paper on fast reactor nuclear fuel.

    Table of Contents

    Meeting Future Power Needs in Licensing Space

    Usnrc Research on Reactor Pressure Vessel Steel Embrittlement

    Irradiation Creep due to SIPA Under Cascade Damage Conditions

    A Model for Interstitial Loop Formation in Concentrated Alloys During Irradiation

    Predictions of Interfacial Phosphorus Segregation in Irradiated Ferritic Steels

    Segregation Effects in Ferritic Fe-Cr Alloys

    Neutron Irradiation Damage and Hardness Anisotropy in Molybdenum Single Crystals

    Strengthening of Chromium Films by 75 Mev Ni Ion Irradiation

    Radiation Damage Rate Measurements in Nickel

    Effects of Fission and Fusion Neutron Irradiations on Mechanical Properties and Defect Recovery Behavior in α-Iron

    Subsize Specimen Testing of a Nuclear Reactor Pressure Vessel Material

    The Effect of Loading Rate Upon Irradiation Embrittlement Measured by Fracture Mechanical Properties

    Effects Of Irradiation Temperature on Embrittlement of Nuclear Pressure Vessel Steels

    Study on the Irradiation Embrittlement of a Microalloyed Ferritic Steel

    Comparison of Drop-Weight and Instrumented Charpy Impact Test Results for Irradiated RPV Steels

    Fracture Toughness and Impact Tests on Neutron Irradiated Ferritic Steels : Results and Correlations

    Development and Application of an LWR Reactor Pressure Vessel-Specific Flaw Distribution

    Effects of Irradiation Temperature on Charpy and Tensile Properties of High-Copper, Low Upper-Shelf, Submerged-Arc Welds

    Evaluation of Thermal-Aged Plates, Forgings, and Submerged-Arc Weld Metals

    Effect of Specimen Size on the Impact Properties of a Pressure Vessel Weld Material

    Further Microstructural Characterization of Submerged-Arc Weld Metals - II

    Exploratory Studies of the Effects of Irradiation Temperature on Mechanical Properties of Structural Steels amd Welds

    The Radiation Hardening and Embrittlement of a Mild Steel Submerged-Arc Weld

    Annealing Experiments on Irradiated NiCrMo Weld Metal

    Degradation of Mechanical Properties of Stainless Steel Cladding Due to Neutron Irradiation and Thermal Aging

    The Effect of Flux on the Irradiation Hardening of Pressure Vessel Steels

    Modeling the Influence of Irradiation Temperature and Displacement Rate on Hardening Due to Point Defect Clusters in Ferritic Steels

    The Modelling of Radiation Hardening and Embrittlement in Magnox Mild Steel Submerged-Arc Welds

    Irradiation Induced Precipitation in Model Alloys with Systematic Variation of Cu, Ni and P Content: A Small Angle Neutron Scattering Study

    Characterisation of Model Fe-Cu-Mn-Ti-N Alloys by Electron Microscopy and Positron Annihilation

    An APFIM Survey of Grain Boundary Segregation and Precipitation in Irradiated Pressure Vessel Steels

    Investigation of Neutron Irradiated Soviet-type Reactor Pressure Vessel Steels by Small Angle Neutron Scattering

    Influence of Some Alloying Elements on the Formation of Vacancy Defects in Ferritic Steels During Irradiation at 288°C

    Metallurgical Considerations in the Application of DPA to Reactor Vessel Analysis

    Postirradiation Deformation Behavior in Ferritic Fe-Cr Alloys

    Tensile and Fracture Mechanics Properties of Neutron Irradiated Manet I (Martensitic 11Cr Steel Type DIN 1.4914)

    Influence of Cold Work, Heat Treatment, and Chromium Content on the Fracture Properties of Irradiated Martensitic Steels

    Charpy Impact Toughness of Martensitic Steels Irradiated in FFTF: Effect of Heat Treatment

    Microstructural Studies in Fast Reactor Irradiated FV448 Ferritic-Martensitic Alloy Plate and Weldment

    Effects of Neutron Irradiation on the Notch Ductility of 15MnTi Steel

    The Influence of Specimen Size on Measurement of Thermal or Irradiation Creep in Pressurized Tubes

    Tensile Properties of Neutron Irradiated 316Ti and 15-15Ti Steels

    Mechanical Property Degradation of Fast Reactor Fuel Cladding During Thermal Transients

    Fatigue Crack Growth Properties of Thermal Reactor Irradiated Nimonic PE16

    Influence of Cold Work on the Irradiation Creep and Creep Rupture of Titanium Modified Austenitic Stainless Steel

    Mechanical Properties of 1950's Vintage Type 304 Stainless Steel Weldment Components After Low Temperature Neutron Irradiation

    Effects of Neutron Irradiations at Temperatures Below 500°C on the Properties of Cold Worked 316 Stainless Steels: A Review

    Technique to Eliminate Helium Induced Weld Cracking in Stainless Steels

    Helium-Induced Weld Degradation of HT-9 Steel

    The Complex Action of Major Solutes on Radiation-Induced Swelling of Fe-Cr-Ni Austenitic Alloys

    Radiation Creep and Swelling of Austenitic 16Cr-15Ni-3Mo-Nb Steels Irradiated in the Reactor BOR-60 at 350 and 420 C

    Swelling and Irradiation Creep of Neutron-Irradiated 316Ti and 15-15Ti Steels

    Influence of Aluminum and Titanium on Gas Bubble Microstructure Formation in Nickel Under Helium-Ion Irradiation

    Stress Corrosion Cracking Susceptibility of Irradiated Type 304 Stainless Steels

    Radiation-Induced Solute Segregation and Stress Corrosion Cracking Study of AISI 304 and AISI 304L Stainless Steels

    Influence of Impurities and Alloying Elements on IASCC in Neutron Irradiated Austenitic Stainless Steels

    The Relationship of Grain Boundary Composition in Irradiated Type 304SS to Neutron Fluence and IASCC

    Isotopic Tailoring with 59Ni to Study Helium Generation Rates and Their Effect on Tensile Properties of Neutron-Irradiated Fe-Cr-Ni Alloys

    Microstructural and Microchemical Evolution During Fast Neutron Irradiation in Nickel and Nickel-Silicon Alloys Doped with Isotopically Controlled Boron

    The Effect of Phosphorus on the Microstructure of an Fe-16Cr-17Ni Austenitic Ternary Induced by Fast Neutron Irradiations

    Void Formation and Induced-Segregation During Electron-Irradiation in Ti and Nb Modified Austenitic Steels

    Effects of Applied Stress on Microstructural Evolution in 316SS Under Ion Irradiation

    The Observation and Interpretation of Microstructural Evolution and Swelling in Austenitic Steels Under Irradiation

    Effects of Cascade Damage and Helium Production Under 600 MeV Proton Irradiation of Cu and Cu-Al2O3

    The Role of Nickel and Zinc in Defect Behavior and Microstructural Evolution of Copper Under Electron Irradiation

    Mechanical Properties of Induction Brazed Glidcop Al-15

    The Response of Dispersion-Strengthened Copper Alloys to High Fluence Neutron Irradiation at 415°C

    Effects of Hot Implantation of Helium in Copper on Bubble Formation Within Grains and on Grain Boundaries

    Evolution of Microstructure in Zirconium Alloy Core Components of Nuclear Reactors during Service

    Modelling the Effect of Texture and Dislocation Structure on Irradiation Creep of Zirconium Alloys

    Strain Hardening Parameter Evaluation of Irradiated Zircaloy—2

    Irradiation Growth of Zirconium Alloys

    The Effect of Irradiation on the Mechanical Properties of 6061-T651 Aluminum

    Effects of High Thermal Neutron Fluences on Type 6061 Aluminum

    Irradiation-Induced Precipitation in Vanadium-Base Alloys Containing Titanium

    Fatigue Crack Growth of Neutron Irradiated V-15Cr-5Ti and V-3Ti-1Si

    Mechanical Properties of Vanadium Alloys Doped with Helium Using Various Techniques

    Measurement of Electrical Conductivity of Ceramic Insulators in a Fission Reactor

    Radiation Induced Mechanical Stresses in Polycrystalline Alumina Insulators

    High-Temperature Irradiation of Alumina-Base Ceramic Materials in a Water Cooled Fission Reactor

    The Effect of Neutron Irradiation on the Structure and Properties of Carbon-Carbon Composite Materials

    Irradiation Behavior of Carbon-Boron-Titanium Materials

    The Role of Phase-Boundary Fission-Gas Bubbles in the Cavitational Swelling of Irradiated U-Pu-Zr Fuel

    Effect of Neutron Irradiation on Thermal Conductivity of Carbon/Carbon Fiber Materials at 400 and 600°C in the Fluence Range 1 × 1022 to 1 × 1024 m-2

    Author Index

    Subject Index

    Committee: E10

    DOI: 10.1520/STP1175-EB

    ISBN-EB: 978-0-8031-5262-5

    ISBN-13: 978-0-8031-1488-3

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