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    Effects of Radiation on Nuclear Materials and the Nuclear Fuel Cycle: 24th Volume

    Busby Jeremy, Hanson Brady
    Published: 2010

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    Fifteen peer-reviewed papers examine radiation damage for the entire fuel cycle. Topics cover:
    • Surveillance programs around the world
    • Detailed characterization of irradiated microstructures
    • Radiation effects in oxide-dispersion strengthened alloys and austenitic stainless steels
    • Modeling helium bubbles
    • Finite-element modeling of fuel bundles
    • And much more!

    Table of Contents

    International Atomic Energy Agency Coordinated Research Projects on Structural Integrity of Reactor Pressure Vessels

    Analysis of the Belgian Surveillance Fracture Toughness Database Using Conventional and Advanced Master Curve Approaches

    Final Results from the Crack Initiation and Arrest of Irradiated Steel Materials Project on Fracture Mechanical Assessments of Pre-Irradiated RPV Steels Used in German PWR

    Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel Materials

    Magnox Steel Reactor Pressure Vessel Monitoring Schemes—An Overview

    Investigation of Beltline Welding Seam of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel

    Microstructural Characterization of RPV Materials Irradiated to High Fluences at High Flux

    Irradiation-Induced Grain-Boundary Solute Segregation and Its Effect on Ductile-to-Brittle Transition Temperature in Reactor Pressure Vessel Steels

    Irradiation-Induced Hardening and Embrittlement of High-Cr ODS Ferritic Steels

    Kinetic Monte Carlo Simulation of Helium-Bubble Evolution in ODS Steels

    Study of Microstructure and Property Changes in Irradiated SS316 Wrapper of Fast Breeder Test Reactor

    Unusual Enhancement of Ductility Observed during Evolution of a “Deformation Wave” in 12Cr18Ni10Ti Stainless Steel Irradiated in BN-350

    Interrelationship between True Stress—True Strain Behavior and Deformation Microstructure in the Plastic Deformation of Neutron-Irradiated or Work-Hardened Austenitic Stainless Steel

    Influence of Neutron Irradiation on Energy Accumulation and Dissipation during Plastic Flow and Hardening of Metallic Polycrystals

    Comparison of CANDU Fuel Bundle Finite Element Model with Unirradiated Mechanical Load Experiments

    Author Index

    Subject Index

    Committee: E10

    DOI: 10.1520/STP1513-EB

    ISBN-EB: 978-0-8031-8417-6

    ISBN-13: 978-0-8031-3425-6

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