Zirconium in the Nuclear Industry: 15th International Symposium

    Kammenzind Bruce, Limbäck Magnus
    Published: 2009

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    The latest in this popular series provides 44 peer-reviewed papers on the latest international research covering all aspects of zirconium alloy properties and performance relevant to the nuclear industry.

    Topics address:

    • All aspects of the fuel cycle

    • Basic metallurgy

    • Spent fuel

    • Corrosion

    • Mechanical properties

    • Deformations mechanisms

    • Failure mechanisms

    • LOCA and Transients.

    These papers provide examples of studies where experimental techniques are combined with analytical tools and calculations; reflect a stronger trend towards efforts that enable fundamental in-reactor measurements, which are essential for further development of experimental techniques as well as for the possibility to enhance the development of improved alloys; and examine an increasing number of alternative alloys being developed and verified.

    Table of Contents

    In-Reactor Deformation of Zirconium Alloy Components
    Holt R.

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

    Characterization of Zirconium Hydrides and Phase Field Approach to a Mesoscopic-Scale Modeling of Their Precipitation
    Ambard A., Blat-Yrieix M., Kihn Y., Legras L., Legris A., Morniroli J., Thuinet L., Zhao Z.

    Influence of Structure Changes in E110 Alloy Claddings on Ductility Loss under LOCA Conditions
    Belov V., Lyaschenko N., Mal'gin A., Nikulin S., Nikulina A., Rozhnov A.

    Investigations of the Microstructure and Mechanical Properties of Prior-β Structure as a Function of the Oxygen Content in Two Zirconium Alloys
    Barcelo F., Brachet J., Hamon D., Lesbros A., Maillot V., Mardon J., Pineau A., Poissonnet S., Stern A.

    Hydrogen Content, Preoxidation, and Cooling Scenario Effects on Post-Quench Microstructure and Mechanical Properties of Zircaloy-4 and M5® Alloys in LOCA Conditions
    Brachet J., Gilbon D., Lesbros A., Mardon J., Portier L., Vandenberghe-Maillot V., Waeckel N.

    Experimental and Analytical Investigation of the Mechanical Behavior of High-Burnup Zircaloy-4 Fuel Cladding
    Billone M., Daum R., Majumdar S.

    Effect of Local Hydride Accumulations on Zircaloy Cladding Mechanical Properties
    Gavillet D., Hermann A., Yagnik S.

    Fracture Toughness of Hydrided Zircaloy-4 Sheet under through-Thickness Crack Growth Conditions
    Chan K., Koss D., Motta A., Raynaud P.

    Characterization of Local Strain Distribution in Zircaloy-4 and M5® Alloys
    Barberis P., Bornert M., Bretheau T., Crépin J., Doumalin P., Elbachiri K., Rebeyrolle V.

    In-Pile Criteria for the Initiation of Massive Hydriding of Zr in Steam-Hydrogen Environment
    Evdokimov I., Likhanskii V.

    Round-Robin Testing of Fracture Toughness Characteristics of Thin-Walled Tubing
    Adamson R., Bertsch J., Efsing P., Fukuda T., Grigoriev V., Kuo R., Mahmood S., Oberländer B., Ramasubramanian N., Sainte-Catherine C., Yagnik S.

    Role of Twinning and Slip in Deformation of a Zr-2.5Nb Tube
    Kim Y.

    Measurement of Rates of Delayed Hydride Cracking (DHC) in Zr-2.5Nb Alloys—An IAEA Coordinated Research Project
    Coleman C., Inozemtsev V.

    A Study of the Structure and Chemistry in Zircaloy-2 and the Resulting Oxide After High Temperature Corrosion
    Dahlbäck M., Hutchinson B., Lehtinen B., Limbäck M.

    Effects of Pt Surface Coverage on Oxidation of Zr and Other Materials
    Anghel C., Hultquist G., Limbäch M., Szakalos P.

    Studies of Corrosion of Cladding Materials in Simulated BWR Environment using Impedance Measurements
    Ahlberg E., Forsberg S., Limbäch M.

    In Situ EIS Measurements of Irradiated Zircaloy-4 Post-Transition Corrosion Kinetic Behavior
    Eklund K., Kammenzind B., Rishel D.

    Effect of Water Chemistry and Composition on Microstructural Evolution of Oxide on Zr Alloys
    Chu Y., Li Q., Liu W., Yao M., Zhou B.

    The Effect of Hydrogen on the Transition Behavior of the Corrosion Rate of Zirconium Alloys
    Harada M., Wakamatsu R.

    A New Model to Predict the Oxidation Kinetics of Zirconium Alloys in a Pressurized Water Reactor
    Ambard A., Bénier G., Bouineau V., Duverneix T., Fayette L., Godlewski J., Pêcheur D.

    In PWR Comprehensive Study of High Burn-Up Corrosion and Growth Behavior of M5® and Recrystallized Low-Tin Zircaloy-4
    Blat M., Bossis P., Chabretou V., Dalmais A., Doriot S., Gilbon D., Mardon J., Miquet A., Verhaeghe B.

    ZIRLO™ Cladding Improvement
    Comstock R., Foster J., Yueh H.

    Corrosion and Oxide Properties of HANA Alloys
    Choi B., Jeong Y., Park J., Yoo S.

    Microstructural Characterization of Oxides Formed on Model Zr Alloys Using Synchrotron Radiation
    Cai Z., Comstock R., Gomes da Silva M., Lai B., Motta A., Yilmazbayhan A.

    Chemistry of Waterside Oxide Layers on Pressure Tubes
    Do T., Hocking W., Saidy M.

    Manufacturing Variability, Microstructure, and Deformation of Zr-2.5Nb Pressure Tubes
    Bickel G., Griffiths M.

    Effect of Irradiation Damage on the Deformation Properties of Zr-2.5Nb Pressure Tubes
    Buyers A., Donohue S., Griffiths M., Wang N.

    Determination and Interpretation of Texture Evolution during Deformation of a Zirconium Alloy
    Allen V., Comstock R., Daymond M., Preuss M., Quinta da Fonseca J., Robson J.

    Irradiation-Induced Growth and Microstructure of Recrystallized, Cold Worked and Quenched Zircaloy-2, NSF, and E635 Alloys
    Dubecky M., Kobylyansky G., Lin Y., Mahmood S., Nikulina A., Novoselov A., Obukhov A., Ostrovsky Z., Peregud M., Shishin V., Shishov V., White D.

    Deformation Anisotropy of Annealed Zircaloy-2 as a Function of Fast Neutron Fluence
    Griffiths M., Theaker J., Wei X.

    Toward a Better Understanding of Dimensional Changes in Zircaloy-4: What is the Impact Induced by Hydrides and Oxide Layer?
    Ambard A., Beguin S., Blat-Yrieix M., Cayet N., Foct F., Miquet A.

    CASTA DIVA®: Experiments and Modeling of Oxide-Induced Deformation in Nuclear Components
    Barberis P., Chabretou V., Rebeyrolle V., Vassault J., Vermoyal J.

    Cladding Tube Deformation Test for Stress Reorientation of Hydrides
    Alam A., Hellwig C.

    Evaluation of Hydride Reorientation Behavior and Mechanical Properties for High-Burnup Fuel-Cladding Tubes in Interim Dry Storage
    Aomi M., Baba T., Kamimura K., Miyashita T., Shinohara Y., Takeda T., Yasuda T.

    Experimental and Modeling Approach of Irradiation Defects Recovery in Zirconium Alloys: Impact of an Applied Stress
    Béchade J., Barbu A., Cappelaere C., Doriot S., Lemaignan C., Onimus F., Rabouille O., Ribis J.

    Mechanical Properties of Zr-2.5Nb Pressure Tubes Made from Electrolytic Powder
    Coleman C., Griffiths M., Grigoriev V., Kiseliov V., Markelov V., Rodchenkov B.

    Structure-Phase State, Corrosion and Irradiation Properties of Zr-Nb-Fe-Sn System Alloys
    Khokhunova T., Kobylyansky G., Kon'kov V., Markelov V., Nikulina A., Novikov V., Novoselov A., Obukhov A., Ostrovsky Z., Peregud M., Shishov V.

    Investigation of Structural and Chemical Uniformity of Zr2.5% Nb and E635 Alloy by Radioactive Indicators
    Arzhakova V., Belov V., Kabanov A., Kurapov V., Kurapova L., Shikov A., Shtutsa M., Ziganshin A.

    Contribution of Thermodynamic Calculations to Metallurgical Studies of Multi-Component Zirconium Based Alloys
    Barberis P., Brachet J., Dupin N., Joubert J., Servant C., Toffolon-Masclet C., Zeller P.

    Intergranular and Interphase Constraints in Zirconium Alloys
    Cai S., Daymond M., Holt R., Xu F.

    Tearing Crack Growth and Fracture Micro-Mechanisms Under Micro Segregation in Zr-2.5%Nb Pressure Tube Material
    Kapoor K., Kashyap B., Ramana Rao A., Saibaba N.

    Author Index

    Subject Index

    Committee: B10

    DOI: 10.1520/STP1505-EB

    ISBN-EB: 978-0-8031-8007-9

    ISBN-13: 978-0-8031-4514-6

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