Radiation Embrittlement and Surveillance of Nuclear Reactor Pressure Vessels: An International Study

    Steele LE
    Published: 1983

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    STP 819 presents an international view on this subject drawing particularly on experience in laboratory studies and operating nuclear power plants in the USA and Europe. Of particular interest to the reader is the information imparted on reactor vessel embrittlement determination through periodic surveillance of specimens exposed in operating nuclear plants.

    Table of Contents

    Steele L.

    Steele L.

    NRC Safety Research Priorities for Reactor Vessel Embrittlement, Annealing, and Surveillance Dosimetry
    Serpan C.

    West German Research Programs on Irradiation Effects on Reactor Pressure Vessels
    Kussmaul K.

    Irradiation Embrittlement of Pressure Vessel Steels: A Review of Activities in France
    Petrequin P.

    Determination of Neutron Damage Parameters for Irradiation Embrittlement
    Lippincott E., McElroy W.

    Effect of Irradiation on Elastic-Plastic Toughness of Pressure Vessel Steels
    Houssin B., Petrequin P., Soulat P.

    Specific Problems of Reactor Pressure Vessels Related to Irradiation Effects
    Kussmaul K.

    Status of Knowledge of Radiation Embrittlement in U.S. Reactor Pressure Vessel Steels
    Hawthorne J.

    Irradiation Experiments in the Testing Nuclear Power Plant VAK
    Anders D., Föhl J., Leitz C.

    Role of the Active Defect Complex in the Neutron Embrittlement and Thermal Recovery of High-Copper Reactor Pressure Vessel Steels
    Highton J.

    Survey of Utility Experience with Reactor Vessel Surveillance
    Rothstein S.

    Thermal Aging Capsule Results from Oconee Nuclear Station—Unit 1
    Lowe A.

    Assessing Steady-State Neutron Exposure Effects Through Analyses of Reactor Vessel Surveillance Data
    Mager T., Martson T., Yanichko S.

    Selection of Specimen Types for Irradiation Surveillance Programs
    Njo D., Varga T.

    A Fracture Energy Criterion for Irradiation Research and Surveillance
    Gillemot F., Kapitány A.

    Problems in the Evaluation of Reactor Vessel Surveillance Capsules
    Perrin J.

    A Service Laboratory's View of the Status and Direction of Reactor Vessel Surveillance
    Norris E.


    Committee: E10

    DOI: 10.1520/STP819-EB

    ISBN-EB: 978-0-8031-4885-7

    ISBN-13: 978-0-8031-0263-7

    ASTM International is a member of CrossRef.