STP1467

    Zirconium in the Nuclear Industry: Fourteenth International Symposium

    Rudling P, Kammenzind B

    Pages: 918

    Published: 2005

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    Forty-one peer-reviewed papers cover all aspects of the fuel cycle. The Basic Metallurgy and Processing sections represent the beginning of the fuel cycle from component design and manufacture. The BWR Corrosion, PWR Corrosion, and Deformation Mechanism sections represent component performance under nominal service conditions. The Primary Failure Mechanism and the Transient and High Temperature Performance sections cover aspects that might end the useful service life of the component. The remaining papers deal with post service life of the component in a dry storage and in a repository environment.


    Table of Contents

    ZIRLO™ — An Alloy Development Success
    Sabol G.

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

    Plastic Deformation of Irradiated Zirconium Alloys: TEM Investigations and Micro-Mechanical Modeling
    Béchade J., Doriot S., Gilbon D., Legras L., Mardon J., Monnet I., Onimus F., Pilvin P., Prioul C., Robert L., Verhaeghe B.

    Study of Nb and Fe Precipitation in α-Phase Temperature Range (400 to 550°C) in Zr-Nb-(Fe-Sn) Alloys
    Barberis P., Brachet J., Legras L., Mardon J., Toffolon-Masclet C.

    On Secondary β-Nb Phase Precipitation within Primary α-Zr Phase in Zr-Nb Alloys During Tensile Deformation
    Kapoor K., Kashyap B., Padmaprabu C., Paul T., Rao M., Rao S., Saibaba N., Sanyal T., Saroja S.

    Microstructure and Phase Control in Zr-Fe-Cr-Ni Alloys: Thermodynamic and Kinetic Aspects
    Barberis P., Dupin N., Grange J., Lemaignan C., Pasturel A.

    Modeling of the Simultaneous Evolution of Vacancy and Interstitial Dislocation Loops in hcp Metals Under Irradiation
    Abyzov A., Dubinko V., Griffiths M., Turkin A.

    Microstructural Stability of M5™ Alloy Irradiated up to High Neutron Fluences
    Béchade J., Doriot S., Gilbon D., Legras L., Mardon J., Mathon M.

    Microstructure and Growth Mechanism of Oxide Layers Formed on Zr Alloys Studied with Micro-Beam Synchrotron Radiation
    Cai Z., Comstock R., Lai B., Motta A., Partezana J., Sabol G., Yilmazbayhan A.

    Simulation of Cold Pilgering Process by a Generalized Plane Strain FEM
    Honda A., Horada M., Toyoshima S.

    Temperature and Strain Rate Effects on Zr-1%Nb Alloy Deformation
    Belov V., Bocharov O., Filippov V., Kabanov A., Kotrekhov V., Losistskiy A., Rozhdestvenski V., Shikov A., Zavodchikov S.

    Phase Composition, Structure, and Plastic Deformation Localization in Zr1%Nb alloys
    Arzhakova V., Belov V., Bocharov O., Cheremnykh G., Filippov V., Poletika T., Shikov A., Zavodchikov S., Zuev L.

    The Effect of Beta-Quenching in Final Dimension on the Irradiation Growth of Tubes and Channels
    Andersson T., Askeljung P., Barberis P., Bunel G., Dahlbäck M., Flygare J., Hallstadius L., Lehtinen B., Limbäck M., Massih A., Simonot C.

    Destruction of Crystallographic Texture in Zirconium Alloy Tubes
    Bryk V., Chernyayeva T., Grytsyna V., Krasnorutskyy V., Malykhin D., Stukalov A., Voyevodin V.

    Improved ZIRLO™ Cladding Performance through Chemistry and Process Modifications
    Colburn D., Comstock R., Dahlback M., Hallstadius L., Kesterson R., Shah H., Yueh H.

    Role of Iron for Hydrogen Absorption Mechanism in Zirconium Alloys
    Furuya T., Ishii Y., Itagaki N., Kakiuchi K., Miyazaki A., Suzuki S., Terai T., Yamawaki M.

    In-Situ Studies of the Oxide Film Properties on BWR Fuel Cladding Materials
    Bojinov M., Hansson-Lyyra L., Kinnunen P., Saario T., Sirkiä P.

    The Correlation Between Microstructures and in-BWR Corrosion Behavior of Highly Irradiated Zr-based Alloys
    Etoh Y., Ishimoto S., Kubo T., Kubota O., Ogata K., Takagawa Y.

    Effect of Alloying Elements and Impurities on in-BWR Corrosion of Zirconium Alloys
    Garzarolli F., Sell H., Trapp-Pritsching S.

    In-Core Tests of Effects of BWR Water Chemistry Impurities on Zircaloy Corrosion
    Cheng B., Ibe H., Ichikawa N., Kubota O., Lutz D., Shimada S.

    Shadow Corrosion Mechanism of Zircaloy
    Lysell G., Nystrand A., Ullberg M.

    TEM Examinations of the Metal-Oxide Interface of Zirconium Based Alloys Irradiated in a Pressurized Water Reactor
    Abolhassani S., Aeschbach F., Bart G., Goll W., Groeschel F., Hoffelner W., Rebac T., Restani R.

    Comparison of the High Burn-Up Corrosion on M5 and Low Tin Zircaloy-4
    Blat M., Bossis P., Hanifi K., Pêcheur D., Thomazet J.

    The Effect of Duplex Cladding Outer Component Tin Content on Corrosion, Hydrogen Pick-up, and Hydride Distribution at Very High Burnup
    Andersson T., Arborelius J., Dahlbäck M., Hahn M., Hallstadius L., Jourdain P., Lisdat R., Toscano E.

    Predicting Oxidation and Deuterium Ingress for Zr-2.5Nb CANDU Pressure Tubes
    Bahurmuz A., Muir I., Urbanic V.

    Inhibitors for Reducing Hydrogen Ingress During Corrosion of Zirconium Alloys
    Donner A., Elmoselhi M.

    Identification of Crystalline Behavior on Macroscopic Response and Local Strain Field Analysis: Application to Alpha Zirconium Alloys
    Crépin J., Dexet M., Gélébart L., Roos A., Sauzay M.

    Ductility of Zircaloy-4 Fuel Cladding and Guide Tubes at High Fluences
    Hermann A., Kuo R., Yagnik S.

    Thermal Creep of Irradiated Zircaloy Cladding
    Billone M., Tsai H.

    Use of the Irradiation-Thermal Creep Model of Zr-1 % Nb Alloy Cladding Tubes to Describe Dimensional Changes of VVER Fuel Rods
    Kanashov B., Nuzhdov A., Polenok V., Rogozyanov A., Smirnov A.

    Influence of Structure—Phase State of Nb Containing Zr Alloys on Irradiation-Induced Growth
    Kobylyansky G., Nikulina A., Novoselov A., Obukhov A., Ostrovsky Z., Peregud M., Pimenov Y., Shishov V.

    Damage Dependence of Irradiation Deformation of Zr-2.5Nb Pressure Tubes
    Christodoulou N., Donohue S., Griffiths M.

    Delayed Hydrogen Cracking Velocity and J-Integral Measurements on Irradiated BWR Cladding
    Grigoriev V., Jakobsson R.

    Overload Fracture of Flaw Tip Hydrides in Zr-2.5Nb Pressure Tubes
    Cui J., Perovic V., Shek G.

    Effect of Irradiation on the Fracture Properties of Zr-2.5Nb Pressure Tubes at the End of Design Life
    Davies P., Griffiths M., Pan Z., Sagat S., St Lawrence S.

    Effect of Fabrication Variables on Irradiation Response of Crack Growth Resistance of Zr-2.5Nb
    Coleman C., Kidd K., Theaker J.

    Fretting-Wear Behavior of Zircaloy-4, OPTIN™, and ZIRLO™ Fuel Rods and Grid Supports under Various Autoclave and Hydraulic Loop Endurance Test Conditions
    Fisher N., Guérout F., King S., Young M.

    Failure of Hydrided Zircaloy-4 Under Equal-Biaxial and Plane-Strain Tensile Deformation
    Damt R., Glendening A., Koss D., Motta A., Pierron O.

    Mechanical Properties of Zircaloy-4 PWR Fuel Cladding with Burnup 54-64MWd/kgU and Implications for RIA Behavior
    Averty X., Bernaudat C., Cazalis B., Desquines J., Poussard C., Yvon P.

    The Effect of Liner Component Iron Content on Cladding Corrosion, Hydriding, and PCI Resistance
    Alvarez A., Andersson T., Díaz M., Dahlbäck M., Engman U., Hallstadius L., Izquierdo J., Jakobsson R., Limbäck M., Massih A., Remartinez B., Sacedon J., Vesterlund G., Witt P.

    Influence of Long Service Exposures on the Thermal-Mechanical Behavior of Zy-4 and M5™ Alloys in LOCA Conditions
    Brachet J., Bredel T., Lesbros A., Maillot V., Mardon J., Portier L.

    Author Index

    Subject Index


    Committee: B10

    Paper ID: STP1467-EB

    DOI: 10.1520/STP1467-EB

    ISBN-EB: 978-0-8031-5519-0

    ISBN-PRINT: 978-0-8031-3493-5

    ASTM International is a member of CrossRef.

    0-8031-3493-2
    978-0-8031-3493-5
    STP1467-EB