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    Zirconium Production and Technology: The Kroll Medal Papers 1975-2010

    Adamson Ronald
    Published: 2010

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    This one-of-a-kind publication provides 30 peer-reviewed, award-winning papers from recipients of the William J. Kroll Zirconium Medal, named in honor of Dr. William J. Kroll, one of the foremost metallurgists of the 20th Century. The Kroll Medal was established to recognize outstanding achievement in the scientific, technological, or commercial aspects of zirconium production and utilization, and to encourage future efforts, studies, and research.

    These peer-reviewed papers cover all aspects of zirconium technology, including history, ore refinement, production, fabrication, mechanical properties, and physical properties. Many of the early papers deal with state-of-the-art ore refinement and Zr production processes, and the later papers with highly sophisticated metallurgical and scientific technologies. Of the 33 medals awarded, 31 have been for work in the commercial nuclear power industry.

    This retrospective covers work conducted in the United States, Canada, Japan, Russia, and Western Europe, including, France, Germany, Sweden, and United Kingdom.

    The papers include a whole range of zirconium alloy technical topics, including:
    • Irradiation effects
    • Evolution of the industry
    • Product development
    • Production
    • Corrosion
    • Deformation mechanisms
    • Basic microstructures
    • Alloy development
    • Hydrogen effects

    Taken overall, the papers provide a comprehensive technical history of zirconium technology and will be of great interest to both young and experienced workers in the field.

    Table of Contents

    Introduction to the Kroll Zirconium Medal Papers Book
    Adamson R.

    The Decision to Use Zirconium in Nuclear Reactors
    Rickover A.

    Towards an Understanding of Zirconium Alloy Corrosion
    Cox B.

    Zirconium Technology—Twenty Years of Evolution
    Lustman B.

    Extractive Metallurgy of Zirconium—1945 to the Present
    Stephens W.

    Anisotropy in Zircaloy
    Picklesimer M.

    Mechanistic Modeling of Zircaloy Deformation and Fracture in Fuel Element Analysis
    Nichols F.

    Zirconium Activities in Europe: 1945–1984
    Syre R.

    Forty-One Years with Zirconium
    Mishima Y., Mishima Y.

    The Origins of the Discovery of the New Cezus Process for Separating Zirconium and Hafnium by Extractive Distillation
    Guerin J., Besson P., Brun P.

    The Irradiation Creep and Growth Phenomena
    Fidleris V.

    Metal Science Aspects of Zirconium-Base Reactor Material Production in the Soviet Union
    Nikulina A.

    Development of Zirconium—Barrier Fuel Cladding
    Armijo J., Coffin L., Rosenbaum H.

    Zirconium Alloy Performance in Light Water Reactors: A Review of UK and Scandinavian Experience
    Pickman D.

    Learning from History: A Case Study in Nuclear Fuel
    Robertson J.

    Behavior and Properties of Zircaloys in Power Reactors: A Short Review of Pertinent Aspects in LWR Fuel
    Garzarolli F., Stehle H., Steinberg E.

    Effects of Neutron Irradiation on Microstructure and Properties of Zircaloy
    Adamson R.

    Understanding Hydrogen in Zirconium
    Sawatzky A., Ells C.

    Microstructure and Properties of Zirconium Alloys in the Absence of Irradiation
    Charquet D.

    Simulating the Behavior of Zirconium-Alloy Components in Nuclear Reactors
    Coleman C.

    Physical Phenomena Concerning Corrosion under Irradiation of Zr Alloys
    Lemaignan C.

    Evolution of the Beta-Quench Process: Kroll Medal Award Presentation, 2001
    Schemel J.

    ZIRLOT™—An Alloy Development Success
    Sabol G.

    Review of Deformation Mechanisms, Texture, and Mechanical Anisotropy in Zirconium and Zirconium Base Alloys
    Tenckhoff E.

    In-Reactor Deformation of Zirconium Alloy Components
    Holt R.

    Microstructure Evolution in Zr Alloys during Irradiation: Dose, Dose Rate, and Impurity Dependence
    Griffiths M.

    Zirconium Corrosion Resistance: Key to Success of the Methanol Carbonylation Acetic Acid Process
    Sanders B.

    Explosion Cladding: An Enabling Technology for Zirconium in the Chemical Process Industry
    Banker J.

    Performance of Zirconium Alloys in Light Water Reactors with a Review of Nodular Corrosion
    Franklin D.

    The Evolution of Microstructure and Deformation Stability in Zr-Nb-(Sn,Fe) Alloys under Neutron Irradiation
    Shishov V.

    The Development of Zr-2.5Nb Pressure Tubes for CANDU Reactors
    Cheadle B.

    Committee: B10

    DOI: 10.1520/RPS2-EB

    ISBN-EB: 978-0-8031-8421-3

    ISBN-PRINT: 978-0-8031-7018-6