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    STP1597

    Zirconium in the Nuclear Industry: 18th International Symposium

    Comstock Robert, Motta Arthur
    Published: 2018


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    Get 43 papers from global researchers on advancements in zirconium technology in the nuclear industry.

    Learn more about the range of challenges for the nuclear community and how they are being addressed in top research presented by industry associates, national laboratories, and universities.

    This publication includes three papers from the 2013, 2014, and 2015 recipients of the William J. Kroll Zirconium Medal. The Kroll Award recognizes outstanding achievement in the scientific, technological or commercial aspects of zirconium production and utilization.

    Topics featured:

    – Processing and Mechanical Properties
    – Mechanisms of Corrosion and Hydrogen Pickup
    – Irradiation Effects on Corrosion
    – Irradiation Damage, Creep, and Growth
    – In-Reactor Performance
    – High-Temperature Transients
    – Hydrogen Effects and Dry Storage

    Special focus areas include waterside corrosion of cladding; accident tolerant fuel cladding; the influence of irradiation on corrosion; characterization of the evolving microstructure at the oxide-metal interface; characterization of oxides formed on E110 and E635 in VVER-1000 reactors; dimensional stability of zirconium alloy components through creep and growth during service; high-temperature behavior of cladding; and accident-tolerant fuel.

    These papers were presented at the 18th International Symposium on Zirconium in the Nuclear Industry, sponsored by ASTM International Committee B10 on Reactive and Refractory Metals and Alloys. It took place May 15-19, 2016, in Hilton Head, South Carolina.



    Committee: B10

    DOI: 10.1520/STP1597-EB

    ISBN-EB: 978-0-8031-7642-3

    ISBN-13: 978-0-8031-7641-6


    978-0-8031-7641-6
    STP1597-EB