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

    Steele LE
    Published: 1989

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    Topics include: Overview of National Programs; Surveillance Program Results; Research to Support Vessel Integrity Assurance; and Fundamental Damage Mechanisms.

    Table of Contents


    Assurance of the Pressure Vessel Integrity with Respect to Irradiation Embrittlement: Activities in the Federal Republic of Germany

    Overview of U.S. Research and Regulatory Activities on Neutron Radiation Embrittlement of Pressure Vessel Steel

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

    The Swiss Research Program on Irradiation Embrittlement and Annealing of Reactor Pressure Vessel Steels

    Evaluation of WWER-440 Surveillance at Paks NPS

    Neutron Embrittlement Surveillance Program at Krṡko Nuclear Power Plant

    Characteristics of the IAEA Correlation Monitor Material for Surveillance Programs

    Irradiation Programs to Establish the Safety Margins of German Licensing Rules Related to RPV Steel Embrittlement

    Development of Reactor Pressure Vessel Design, Neutron Fluence Calculation, and Material Specification to Minimize Irradiation Effects

    Effectiveness of Flux Reduction Measures Instituted at the Maine Yankee Atomic Power Station

    Residual Life Assessment of Light Water Reactor Pressure Vessels

    Radiation Embrittlement Trend Curves and the Impact on Nuclear Plant Operating Criteria

    Evaluation of Thermal Annealing Behavior of Neutron-Irradiated Reactor Pressure Vessel Steels Using Nondestructive Test Methods

    Semiempirical Model for Annealing and Reirradiation Embrittlement in Pressure Vessel Steels

    Status of Research to Assess Radiation Effects on Crack-Arrest Toughness of RPV Steels

    Defect Particles in an Irradiated RPV Steel Studied by a Systematic Variation of Irradiation and Annealing Conditions: Preliminary Results by Small Angle Neutron Scattering

    SANS Investigation of Irradiated A533-B Steels Doped with Phosphorus

    Positron Lifetime Characterization of Irradiated Pressure Vessel Model Alloys

    Committee: E10

    DOI: 10.1520/STP1011-EB

    ISBN-EB: 978-0-8031-5074-4

    ISBN-13: 978-0-8031-1187-5