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    Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Second Volume)

    Steele LE
    Published: 1986

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    STP 909 has sixteen peer-reviewed papers divided into four sections that reflect changes in the nuclear power industry occurring since 1981, including escalating capital requirements and a growing worldwide dependence on nuclear power for electricity production. The four sections of this book are:

    • Overview of National Programs
    • Surveillance and Other Radiation Embrittlement Studies
    • Pressure Vessel Integrity and Regulatory Considerations
    • and Mechanisms of Irradiation Embrittlement.

    Table of Contents


    Overview of Studies in the United Kingdom on Neutron Irradiation Embrittlement of Pressure Vessel Steels


    Irradiation Effects in Reactor Pressure Vessel Steels: A Nuclear Regulatory Commission Perspective

    Irradiation Behavior of Reactor Pressure Vessel Steels from the Research Program on the Integrity of Components

    Surveillance Programs and Irradiation Embrittlement Research of the Loviisa Nuclear Power Plant

    Effect of Irradiation on the Elasto-Plastic Toughness of Pressure Vessel Steels

    Prediction of Reference Transition Temperature Increase Due to Neutron Irradiation Exposure

    Boiling Water Reactor (BWR) Pressure Vessel Surveillance Program

    Static Fracture Criteria Evaluation Using Small Specimens

    Investigations and Measures to Guarantee the Safety of a Pressurized Water Reactor's Pressure Vessel Against Brittle Fracture

    Basis for Revision 2 of the U. S. Nuclear Regulatory Commission's Regulatory Guide 1.99

    Reactor Pressure Vessel Structural Implications of Embrittlement to the Pressurized-Thermal-Shock Scenario

    Safety Standard KTA 3203: Monitoring Radiation Embrittlement of Reactor Pressure Vessels of Light-Water Reactors

    Microanalytical Studies of Pressure Vessel Weld Materials

    Irradiation Embrittlement of Reactor Pressure Vessel Steels: Mechanisms, Models, and Data Correlations

    Annealing and Reirradiation Response of Irradiated Pressure Vessel Steels

    Effect of Various Metallurgical Microstructures on the Response of the Nickel-Molybdenum-Chromium BH 70 Steel to Neutron Irradiation at 285°C

    Author Index

    Subject Index

    Committee: E10

    DOI: 10.1520/STP909-EB

    ISBN-EB: 978-0-8031-4975-5

    ISBN-13: 978-0-8031-0473-0

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