Zirconium in the Nuclear Industry: Twelfth International Symposium

    Sabol GP, Moan GD
    Published: 2000

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    44 papers discuss the history, processing, use, and properties of Zirconium and its alloys. Nearly half are concerned with the corrosion and hydriding of different Zirconium alloys. The techniques used to characterize the oxides and their microstructures and properties have become very advanced. The industry, including producers and users, expects that the work will lead to important conclusions about alloy development, optimization of the processing parameters, and station operating procedures so that the current and new Zirconium materials will continue to operate reliably to very high neutron fluences.

    Seven major topics include:

    • Properties at High Neutron Fluences

    • Hydrogen and Temperature Effects

    • Deformation and Fracture Studies

    • Processing and Alloy Development

    • Effect of Composition and Microstructure on Corrosion

    • Corrosion Simulation and the Effect of the Environment

    • Effects of Oxides on Oxidation and H Pickup Rates

    Audience:Scientists and engineers involved in the production and properties of components for use in nuclear reactors, their behavior during service and the property changes that occur with increasing neutron fluences.

    Table of Contents

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

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

    Understanding Hydrogen in Zirconium
    Ells C., Sawatzky A.

    Irradiation Creep and Growth Behavior, and Microstructural Evolution of Advanced Zr-Base Alloys
    Doriot S., Gilbon D., Mardon J., Soniak A.

    Irradiation-Enhanced Deformation of Zr-2.5Nb Tubes at High Neutron Fluences
    Causey A., Christodoulou N., Ho E., Holt R.

    High-Fluence Irradiation Growth of Cold-Worked Zr-2.5Nb
    Causey A., Griffiths M., Ho E., Holt R.

    Evolution of Dislocation and Precipitate Structure in Zr Alloys Under Long-Term Irradiation
    Averin S., Kozlov A., Nikulina A., Panchenko V., Shishov V., Sinelnikov L.

    Effect of Long-Term Irradiation on the Fracture Properties of Zr-2.5Nb Pressure Tubes
    Coleman C., Davies P., Griffiths M., Hosbons R., Sagat S.

    Post-Irradiation Characterization of Ultra-High-Fluence Zircaloy-2 Plate
    Adamson R., Etoh Y., Farkas D., Mahmood S.

    The Terminal Solid Solubility of Hydrogen in Zirconium Alloys
    Darby E., McMinn A., Schofield J.

    The Long-Range Migration of Hydrogen Through Zircaloy in Response to Tensile and Compressive Stress Gradients
    Bajaj R., Berquist B., Franklin D., Kammenzind B., Kreyns P.

    Influence of Cladding Microstructure on the Low Enthalpy Failures in RIA Simulation Tests
    Garde A.

    Experiment and Modeling of Advanced Fuel Rod Cladding Behavior Under LOCA Conditions: Alpha-Beta Phase Transformation Kinetics and EDGAR Methodology
    Barcelo F., Bernaudat C., Brachet J., Castaing A., Forgeron T., Hivroz J., Mardon J.

    Behavior of Irradiated Zircaloy-4 Fuel Cladding Under Simulated LOCA Conditions
    Goto K., Homma T., Ozawa M., Takahashi T.

    Influence of Texture on the Fracture Toughness of Unirradiated Zircaloy Cladding
    Andersson S., Grigoriev V., Pettersson K.

    Degraded Fuel Cladding Fractography and Fracture Behavior
    Adamson R., Davies J., Edsinger K.

    Delayed Hydride Cracking in Irradiated Zircaloy Cladding
    Efsing P., Pettersson K.

    Size, Geometry, and Material Effects in Fracture Toughness Testing of Irradiated Zr-2.5Nb Pressure Tube Material
    Davies P., Shewfelt R.

    Failure Mechanisms of Irradiated Zr Alloys Related to PCI: Activated Slip Systems, Localized Strains, and Iodine-Induced Stress Corrosion Cracking
    Fregonese M., Lefebvre F., Lemaignan C., Magnin T., Régnard C., Rouillon L.

    Impact of Hydrogen on Plasticity and Creep of Unirradiated Zircaloy-4 Cladding Tubes
    Bouffioux P., Rupa N.

    A New Fabrication Process for Zr-Lined Zircaloy-2 Tubing
    Abe H., Anada H., Furugen M., Takeda K., Uehira A.

    Zirconium Alloy Cold Pilgering Process Control by Modeling
    Aubin J., Montmitonnet P., Mulot S.

    In-Process Investigation of Precipitate Growth in Zirconium Alloys
    Herb B., König A., Ruhmann H.

    Influence of Composition and Fabrication Process on Out-of-Pile and In-Pile Properties of M5 Alloy
    Charquet D., Mardon J., Senevat J.

    Effect of Dilute Alloy Additions of Molybdenum, Niobium, and Vanadium on Zirconium Corrosion
    Comstock R., Nayak U., Sabol G.

    E110 Alloy Cladding Tube Properties and Their Interrelation with Alloy Structure-Phase Condition and Impurity Content
    Belov V., Bibilashvili Y., Kuz'menko N., Lositski A., Nikulina A., Novoselov A., Peregud M., Shebaldov P.

    Contribution to a Better Understanding of the Detrimental Role of Hydrogen on the Corrosion Rate of Zircaloy-4 Cladding Materials
    Amanrich H., Blat M., Legras L., Noel D.

    Mechanism of Corrosion Rate Degradation Due to Tin
    Anada H., Takeda K.

    Influence of Transition Elements Fe, Cr, and V on Long-Time Corrosion in PWRs
    Broy Y., Garzarolli F., Seibold A., Van Swam L.

    Fundamental Study on the Corrosion Mechanism of Zr-0.2Fe, Zr-0.2Cr, and Zr-0.1Fe-0.1Cr Alloys
    Isobe T., Mae Y., Murai T., Takizawa Y.

    Microstructural Aspects of Corrosion and Hydrogen Ingress in Zr-2.5Nb
    Griffiths M., Urbanic V.

    The Effect of Microstructure on the Corrosion Behavior of Zircaloy-2 in BWRs
    Etoh Y., Hayashi H., Kitamura M., Kubo T., Nomata T., Nonaka Y.

    Impact of Second Phase Particles on BWR Zr-2 Corrosion and Hydriding Performance
    Lehtinen B., Pettersson H., Rudling P., Wikmark G.

    Corrosion of Electron-Irradiated Zr-2.5Nb and Zircaloy-2
    Coleman C., Griffiths M., Hutcheon R., McDougall G., Urbanic V., Woo O.

    Evaluation of Zircaloy-2 Cladding Corrosion Characteristics by Simulated BWR Corrosion Loop Test
    Asahi K., Hayashi H., Kitamura M., Kogai T., Nonaka Y., Sakamoto M., Sasaki M., Shimada S., Yamawaki M.

    Studies of Zirconium Alloy Corrosion and Hydrogen Uptake During Irradiation
    Aarrestad O., McDougall G., Urbanic V.

    Behavior of Lithium and Boron in Irradiated and Unirradiated Oxides Formed on Zircaloy-4 Claddings
    Inoue Y., Kido T., Komine I., Takahashi T., Uchida H., Wada S.

    Contribution to the Understanding of the Effect of the Water Chemistry on the Oxidation Kinetics of Zircaloy-4 Cladding
    Fayette L., Frichet A., Godlewski J., Kerrec O., Noé M., Pêcheur D., Peybernès J.

    Correlation Between Characteristics of Oxide Films Formed on Zr Alloys in BWRs and Corrosion Performance
    Etoh Y., Harada H., Ito K., Kubo T., Nanikawa S., Shimada S.

    Electrochemical Examinations in 350°C Water with Respect to the Mechanism of Corrosion-Hydrogen Pickup
    Baur K., Garzarolli F., Ruhmann H., Sell H.

    Hydrogen Transport in the Oxide and Hydrogen Pickup by the Metal During Out- and In-Reactor Corrosion of Zr-2.5Nb Pressure Tube Material
    Leger M., Perovic V., Ramasubramanian N.

    Stress Distribution Measured by Raman Spectroscopy in Zirconia Films Formed by Oxidation of Zr-Based Alloys
    Bouvier P., Fayette L., Godlewski J., Lucazeau G.

    Role of Intermetallic Precipitates in Hydrogen Transport through Oxide Films on Zircaloy
    Hatano Y., Hayashi M., Kitano K., Sugisaki M.

    Multi-Scale Characterization of the Metal-Oxide Interface of Zirconium Alloys
    Barberis P., Bossis P., Iltis X., Lefebvre F., Lelièvre G.

    Author Index

    Subject Index

    Committee: B10

    DOI: 10.1520/STP1354-EB

    ISBN-EB: 978-0-8031-5416-2

    ISBN-13: 978-0-8031-2499-8

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