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    Effects of Radiation on Materials: 19th International Symposium

    Hamilton ML, Kumar AS, Rosinski ST, Grossbeck ML
    Published: 2000

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    STP 1366, the nineteenth volume in this series, examines 90 peer-reviewed papers from the international nuclear community, with the emphasis on advanced materials such as silicon carbide and vanadium alloys. A majority of the papers are devoted to pressure vessel embrittlement and its mitigation. Smaller segments address the issues of light water reactors, fusion reactors, and to a lesser extent, breeder reactors.

    Several emerging issues are also explored, including reduced activation, welding of irradiated materials and damage resulting form high-energy proton beams in accelerator-driven nuclear systems.

    Divided into the following sections:

    • Pressure Vessel Steels--Mechanical Properties

    • Pressure Vessel Welds--Mechanical Properties

    • Pressure Vessel Steels--Segregation and Microstructure

    • Ferritic and Ferritic/Martensitic Steels--Annealing and Reirradiation Behavior

    • Irradiation-Induced Behavior Of Iron, Model Alloys, and Ferritic/Martensitic Alloys

    • Low Activation Ferritic/Martensitic Alloys

    • Irradiation Creep and The Creep-Swelling Relationship

    • Austenitic Alloys--Irradiation-Induced Swelling, Segregation and Microstructure

    • Irradiated Structural Alloys--Welding

    • Experimental Techniques and Facilities

    • Beryllium and Ceramics

    • Other Materials

    This publication will be of interest to research scientists, metallurgists, nuclear engineers, nuclear utilities, nuclear reactor vendors. Also university nuclear engineering and materials sciences departments.

    Committee: E10

    DOI: 10.1520/STP1366-EB

    ISBN-EB: 978-0-8031-5419-3

    ISBN-13: 978-0-8031-2852-1