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

    If you are an ASTM Compass Subscriber and this document is part of your subscription, you can access it for free at ASTM Compass


    Effects of Radiation on Materials: 22nd Symposium

    Allen TR, Lott RG, Busby JT, Kumar AS
    Published: 2006

      Format Pages Price  
    PDF (17M) $98   ADD TO CART
    Hardcopy (shipping and handling) $98   ADD TO CART
    Hardcopy + PDF Bundle - Save 25%
    (shipping and handling)
    $147.00   ADD TO CART

    Cite this document

    X Add email address send
      .RIS For RefWorks, EndNote, ProCite, Reference Manager, Zoteo, and many others.   .DOCX For Microsoft Word

    Thirty-one peer-reviewed papers provide the latest international research on the radiation effects on materials.

    Topics cover:
    • Austenitic stainless steels
    • Ferritic-martensitic stainless steels
    • Embrittlement of pressure vessel steels
    • Radiation damage fundamentals
    • Ceramics for application in Generation IV systems
    • Other nuclear energy system materials

    Table of Contents

    Behavior of Irradiated Type 316 Stainless Steels under Low- Strain-Rate Tensile Conditions

    Radiation-Induced Stress Relaxation of Welded Type 304 Stainless Steel Evaluated by Neutron Diffraction

    Low Strain-Rate Microstructural Deformation Behavior in 316 Stainless Steel Irradiated in EBR-II

    Neutron Flux Effect on the Irradiation Hardening of Type 304 Stainless Steel

    Modeling the Effects of Oversize Solute Additions on Radiation-Induced Segregation in Austenitic Stainless Steels

    Post-Irradiation Tensile Behavior and Residual Activity of Several Ferritic/Martensitic and Austenitic Steels Irradiated in Osiris Reactor at 325°C up to 9 dpa

    The Role of Grain Boundary Engineering on the High Temperature Creep of Ferritic-Martensitic Alloy T91

    Extrapolation of Fracture Toughness Data for HT9 Irradiated at 360–390°C

    Development of Fuel Clad Materials for High Burn-up Operation of LWR

    Small Angle Neutron Scattering Study of Irradiated Martensitic Steels: Relation Between Microstructural Evolution and Hardening

    Radiation Resistance of Advanced Ferritic-Martensitic Steel HCM12A

    Microstructural and Mechanical Characterization of Radiation Effects in Model Reactor Pressure Vessel Steels

    Effects of Neutron Irradiation on Precipitation in Reactor Pressure Vessel Steels

    Radiation- and Thermally-Induced Phosphorus Inter-Granular Segregation in Pressure Vessel Steels

    Fracture Toughness, Thermo-Electric Power, and Atom Probe Investigations of JRQ Steel in I, IA, IAR, and IARA Conditions

    Assessment of Neutron Irradiation-Induced Grain Boundary Embrittlement by Phosphorous Segregation in a Reactor Pressure Vessel Steel

    Effects of Neutron Dose, Dose Rate, and Irradiation Temperature on the Irradiation Embrittlement of a Low-Copper Reactor Pressure Vessel Steel

    Mechanical Property Changes in Reactor Vessel Materials Thermally Aged for 209000 H at 282 °C

    Recent Surveillance Data and a Revised Embrittlement Correlation

    Use of Broken Charpy V-notch Specimens from a Surveillance Program for Fracture Toughness Determination

    Dynamic Finite Element Modeling of Fracture in Charpy V-Notch Specimens of Weld Material 72W

    Effects of Proton Irradiation on Reactor Pressure Vessel Steel and Its Model Alloys

    Correlated Formation and Stability of SIA Loops and Stacking Fault Tetrahedra in High Energy Displacement Cascades in Copper

    Atomic-Scale Simulation of Defect Cluster Formation in High-Energy Displacement Cascades in Zirconium

    Flow Localization Processes in Austenitic Alloys

    Deformation Mechanism Maps of Unirradiated and Irradiated V-4Cr-4Ti

    Plutonium-238 Alpha-Decay Damage Study of A Glass-Bonded Sodalite Ceramic Waste Form

    Microstructure Evolution in ZrC Irradiated with Kr ions

    Mechanical Properties of Cubic Silicon Carbide after Neutron Irradiation at Elevated Temperatures

    Creep-Fatigue Behavior in High Strength Copper Alloys

    Tensile, Flexural, and Shear Properties of Neutron Irradiated SiC/SiC Composites with Different Fiber-Matrix Interfaces

    Committee: E10

    DOI: 10.1520/STP1475-EB

    ISBN-EB: 978-0-8031-5518-3

    ISBN-13: 978-0-8031-3401-0