18th International Symposium on Zirconium in the Nuclear Industry

    Numerical Modeling of Zirconium Alloys Hot Extrusion
    A. Gaillac and P. Barbéris, AREVA NP, Ugine, France

    Texture Development During Rolling of α + β Dual Phase ZrNb Alloys
    C. Daniel, M. Preuss, and J. Quinta da Fonseca, The University of Manchester, Manchester, UK; and P. Honniball and L. Bradley, Rolls-Royce plc, Derby, UK

    Strain-Path Change Tests and Physically Based Polycrystalline Modelling of the Behaviour of Recrystallized Zirconium Alloys
    F. Onimus, M. Bono, J. Garnier, A. Soniak, R. Limon, D. Gilbon, CEA, Gif-Sur-Yvette, France; F. Bourlier, AREVA, Lyon, France; and A. Ambard, EDF R&D, Moret-sur-Loing, France

    Predicting the Flow Stress of Zircaloy-4 Under In-reactor Accident Conditions
    T. Nguyen, M. Preuss and J. Quinta da Fonseca, The University of Manchester, Manchester, UK; J. Romero, Westinghouse Electric Company, Hopkins, SC, USA; and A. Ambard, EDF R&D, Moret-sur-Loing, France

    Mechanical Behavior at High Temperature of Highly Oxygen- or Hydrogen-Enriched α and (Prior-) β Phases of Zirconium Alloys
    M. Le Saux, I. Turque, J. Brachet and V. Vandenberghe, CEA, Gif-sur-Yvette, France; R. Chosson, AREVA NP, Lyon, France; and J. Crépin and A. Gourgues-Lorenzon, Mines ParisTech, Evry, France

    Out-of-Pile R&D on Coated Nuclear Fuel Zirconium Based Claddings for Enhanced Accident Tolerance in LWRs
    J. C. Brachet, I. Idarraga, M. Le Flem, M. Le Saux, F. Schuster, and F. Lomello, CEA, Gif-sur-Yvette, France; J. Bischoff and C. Delafoy, AREVA NP, Lyon, France; and E. Pouiller, EDF R&D, Moret-sur-Loing, France

    High-Resolution Characterization of Zr Nuclear Fuel Cladding Alloys
    J. Hu, B. Setiadinata, T. Aarholt, A. Vilalta-Clemente, A. Wilkinson, M. Moody, C. Grovenor, P. Bagot and S. Lozano-Perez, University of Oxford, Oxford, UK; A. Garner, M. Preuss and P. Frankel, University of Manchester, Manchester, UK; and J. Partezana, Westinghouse Electric Co., Pittsburgh, PA, USA

    Out-of-Reactor Test of Corrosion and Hydrogen Pickup in Fuel Cladding Materials in Contact with Nickel Metal
    D. M. Wells, Electric Power Research Institute, Charlotte, NC, USA; R. Becker and J. Chen, Studsvik Nuclear AB, Nyköping, Sweden; C. Anghel, Westinghouse Electric Sweden, Vasteras, Sweden, D. Hussey, Electric Power Research Institute, Palo Alto, CA, USA, J. Iyer, Westinghouse Electric Company, Columbia, SC, USA; and J. Stevens, AREVA Inc., Lynchburg, VA, USA

    Hydrogen Pick-Up Mechanism in Zirconium Alloys
    A. Couet, University of Wisconsin, Madison, WI, USA; ; A. T. Motta, Pennsylvania State University, University Park, PA, USA; A. Ambard, EDF R&D, Moretsur-Loing, France and R. J. Comstock, Westinghouse Electric Company, Pittsburgh, PA, USA

    Influence of the Hydride Precipitation on the Corrosion Kinetics of Zircaloy-4: Effect of the Nanostructure and Grain Boundaries Properties of Zirconium Oxide Layer on the Oxygen Diffusion Flux
    M. Jublot, G. Zumpicchiat, M. Tupin, K. Colas, S. Pascal and C. Bisor, CEA-Saclay, Gif sur Yvette, France; C. Berdin, University of Paris Sud, Orsay, France; M. Blat, EDF R&D, Moret-sur-Loing, France; and D. Kaczorowski, AREVA NP, Lyon, France

    Microstructure Evolution in Ion-Irradiated Oxidized Zircaloy-4 Studied with Synchrotron Radiation Micro-Diffraction and Transmission Electron Microscopy
    K. B. Colas, R. Verlet, M. Tupin, and M. Jublot, CEA – Saclay, Gif-sur-Yvette, France; Z. Cai, Argonne National Laboratory, Argonne, IL, USA; and K. Wolski, Ecole des Mines de Saint Etienne, Saint Etienne, France

    Understanding of Corrosion Mechanisms after Irradiation: Effect of Ion Irradiation of the Oxide Layers on the Corrosion Rate of M5
    M. Tupin, R. Verlet, S. Miro, M. Jublot, and K. Colas, CEA, Gif-sur-Yvette, France; K. Wolski, Ecole des Mines de Saint Etienne, Saint-Étienne, France; A. Ambard, EDF R&D, Moret-sur-Loing, France; and D. Kaczorowski, AREVA, Lyon, France

    Neutron Irradiation Effects on the Corrosion of Zircaloy-4 in a PWR Environment
    B.F. Kammenzind, J. A. Gruber, R. Bajaj, and J. D. Smee, Bechtel Marine Propulsion Corporation, West Mifflin, PA, USA

    Investigating the Effect of Zirconium Oxide Microstructure on Corrosion Performance: A Comparison Between Neutron, Proton and Non-Irradiated Oxides
    A. Garner, F. Baxter, P. Frankel, M. Topping, A. Harte, T. Slater, and M. Preuss, University of Manchester, Manchester, UK; P. Tejland, Studsvik Nuclear AB, Nyloping, Sweden; J. Romero, Westinghouse Electric Co., Hopkins, SC, USA; E. C. Darby and A. Cole-Baker, Rolls Royce, Derby, UK; and M. Gass, Amec Foster Wheeler, Warrington, UK

    Microbeam X-Ray Absorption Near-Edge Spectroscopy of Oxide Layers in Irradiated Zircaloy-2
    A. Shivprasad and A. T. Motta, The Pennsylvania State University, University Park, PA, USA; A. Kucuk and S. Yagnik, Electric Power Research Institute, Palo Alto, CA, USA; and Z. Cai, Argonne National Laboratory, Argonne, IL, USA

    The Role of Gamma Radiation on Zircaloy-4 Corrosion
    D. M. Rishel and B. F. Kammenzind, Bechtel Marine Propulsion Corporation, West Mifflin, PA, USA

    Study of Structure-Phase State of Oxide Films on E110 and E635 Alloys at Pre- and Post-Irradiation Stages
    A. Shevyakov, V. Novikov and V. Markelov, SC VNIINM, Moscow, Russia; and A. Obukhov and G. Kobylyansky, SC SSC RIAR, Dimitrovgrad, Russia

    Understanding Irradiation Growth through Atomistic Simulations: Defect Diffusion and Clustering, and the Influence of Alloying Elements
    W. Wolf, M. Christensen, C. Freeman and E. Wimmer, Materials Design Inc., Angel Fire, NM, USA; R. B. Adamson, Zircology Plus, Fremont, CA, USA; L. Hallstadius, Westinghouse Electric Sweden, Västerås, Sweden; P. Cantonwine, Global Nuclear Fuels, Wilmington, NC, USA; and E. Mader, Electric Power Research Institute, Palo Alto, CA, USA

    On the Theory of Radiation Growth and Creep of Hexagonal Crystals
    S. Golubov and R. Stoller, Oak Ridge National Laboratory, Oak Ridge, TN, USA; and A. Barashev, University of Tennessee, Knoxville, TN, USA

    Quantifying Irradiation Defects in Zr Alloys: A Comparison between Transmission Electron Microscopy and Whole Pattern Diffraction Line Profile Analysis
    M. Daymond, L. Balogh, F. Long, and Z. Yao, Queen’s University, Kingston, ON, Canada; and M. Preuss, The University of Manchester, Manchester, UK

    Effect of Hydrogen on Irradiation Creep and Growthfor ZIRLO® Alloy and Zr-1.0Nb
    J. P. Foster, G. Pan, L. Cai and A. Atwood, Westinghouse Electric Company, Hopkins, SC, USA

    Effect of Alloying Elements, Cold Work, and Hydrogen on the Irradiation-Induced Growth Behavior of Zirconium Alloy Variants
    S. K. Yagnik, EPRI, Palo Alto, CA, USA; R. Adamson, Zircology Plus, Fremont, CA, USA; G. Kobylyansky and A. Obukhov, JSC SSC RIAR, Dimitrovgrad, Russia; J.-H. Chen, Institute of Nuclear Energy Research, Taiwan; D. Gilbon, CEA-Saclay, Gif-sur-Yvette, France; S. Ishimoto, Global Nuclear Fuel-Japan Co. Ltd, Yokosuka-Shi, Kanagawa-ku, Japan; T. Fukuda, Nuclear Fuel Industries Ltd, Tokai-Mura, Ibaraki, Japan; L. Hallstadius, Westinghouse Electric Sweden, Västerås, Sweden; and S. Mahmood, Pleasanton, CA, USA

    The Effect of Iron on Dislocation Evolution in Model and Commercial Zirconium Alloys
    M. Topping, A. Harte, P. Frankel and M. Preuss, The University of Manchester, Manchester, UK; G. Sundell, M. Thuvander, H.O. Andrén, Chalmers University of Technology, Göteborg, Sweden; S. Dumbill, National Nuclear Laboratories, Seascale, Cumbria, UK; D. Jädernäs and P. Tejland, Studsvik Nuclear, Nyköping, Sweden; J. Romero, Westinghouse Electric Company, Columbia, SC, USA; L. Hallstadius, Westinghouse Electric Sweden, Västerås, Sweden; and E. Darby, Rolls-Royce, Derby, UK

    Equivalent Radiation Damage in Zr-Alloys Irradiated in Various Reactors
    L. Walters, and M. Griffiths, Canadian Nuclear Laboratories Ltd., Chalk River, ON, Canada, S. Douglas, retired from Atomic Energy of Canada Limited, Chalk River, ON, Canada

    Microstructural Evolution of Q12™ Alloy Irradiated in PWR and Comparison with Other Zr Base Alloys
    S. Doriot, B Verhaeghe, A. Soniak, P. Bossis and D. Gilbon, CEA, Gif-sur-Yvette, France; V. Chabretou and J. P. Mardon, AREVA NP, Lyon, France; M. Ton-That, Electricité de France-DIN Septen, Villeurbanne, France; and A. Ambard, Electricité de France, Moret-sur-Loing, France

    Preliminary Irradiation Effect on Corrosion Resistance of Zirconium Alloys
    V. Markelov, V. Novikov, A. Gusev, A. Shevyakov, M Peregud and V. Konkov, SC VNIINM, Moscow, Russia; and S. Eremin, A. Pokrovsky and A. Obukhov SC SSC RIAR, Dimitrovgrad, Russia

    Effects of Chemistry and Microstructure on Corrosion Performance of Zircaloy-2 Based BWR Cladding
    Y.-P. Lin and D. White, Global Nuclear Fuel-Americas, Wilmington, NC, USA; and D. Lutz, Global Nuclear Fuel-Americas, Sunol, CA, USA

    The Performance of NSF in BWR Operating Conditions
    P. Cantonwine and Y.-P. Lin, Global Nuclear Fuel – Americas, Wilmington, NC, USA; and D. Lutz, Global Nuclear Fuel-Americas, Sunol, CA, USA

    Temperature and Neutron Flux Dependence of In-Reactor Creep for Cold-worked Zr 2.5Nb
    R. DeAbreu, G. Bickel, A. Buyers, S. Donohue, K. Dunn, M. Griffiths, and L. Walters,Canadian Nuclear Laboratories, Chalk River, ON, Canada

    In-Pile Testing of CrN, TiAlN and AlCrN Coatings on Zircaloy Cladding in the Halden Reactor
    R. Van Nieuwenhove, IFE, Halden, Norway; and V. Andersson, J. Balak, and B. Oberländer, IFE, Kjeller, Norway

    Alloying Effect of Nb and Sn on the Zirconium Alloy Fuel Claddings Behavior at High Temperature Oxidation in Steam
    A. Malgin, V. Markelov, A. Gusev, A. Nikulina, V. Novikov, and I. Shelepov, SC VNIINM, Moscow, Russia; and V. Donnikov, V. Latunin, and J. Kosihina, JSC VTI, Moscow, Russia

    Post Quench Ductility of Zirconium Alloy Cladding Materials
    A. Mueller, and J. Partezana, Westinghouse Electric Co., Pittsburgh, PA, USA; and G. Pan, D. Mitchell, A. Garde, A. Atwood, and J. Romero, Westinghouse Electric Co., Hopkins, SC, USA

    Investigation and Modeling of the Degradation of Zr-Based Fuel Claddings During Corrosion in Steam and Air-Steam Mixtures at High Temperatures
    F. Haurais, E. Beuzet and M. Torkhani, EDF, Clamart, France; M. Steinbrück, Karlsruhe Institute of Technology, Karlsruhe, Germany; A. Ambard, EDF, Moret-sur-Loing, France; and E. Simoni, Université Paris-Saclay France

    Combined Raman Imaging and 18O Tracer Analysis for the Study of Zircaloy-4 High Temperature Oxidation in Spent Fuel Pool Accident
    A. Kasperski and M. Mermoux, University of Grenoble Alpes, Grenoble, France; and C. Duriez, IRSN, Saint-Paul-lèz-Durance, France

    High Temperature Secondary Hydriding Experiments with E110 and E110G Claddings
    Z. Hózer, I. Nagy, A. Vimi, M. Kunstár, P. Szabó, T. Novotny, E. Perez-Feró, Z. Kis, L. Szentmiklósi, M. Horváth, A. Pintér-Csordás, E. Barsy, and K. Kulacsy, Hungarian Academy of Sciences Centre for Energy Research, Budapest, Hungary ; and M. Grosse, Karlsruhe Institute of Technology, Karlsruhe, Germany

    In-Situ Investigations of the Hydrogen Uptake of Zirconium Alloys During Steam Oxidation
    M. Grosse and M. Steinbrück, Karlsruhe Institute of Technology, Karlsruhe, Germany; B. Schillinger Technical University of Munich, Munich, Germany; and A. Kaestner, Paul Scherrer Institute, Villigen, Switzerland

    Effect of Irradiation on Terminal Solid Solubility of Hydrogen in Zr-2.5Nb
    H. Nordin, V. Hilton, A. Buyers, and C. Coleman, Canadian Nuclear Laboratories, Chalk River, ON, Canada; and G. McRae, Carleton University, Ottawa, ON, Canada

    Hydrogen Trapping at Irradiation Produced Defects
    B. F. Kammenzind, Bechtel Marine Propulsion Corporation, West Mifflin, PA, USA

    Hydride Effects on Discharged Fuel Clad Related to Accident Conditions During Dry Storage and Handling
    R. Kesterson, R. Sindelar, P. Korinko, and P. Lam, Savannah River National Laboratory, Aiken, SC USA

    Is Spent Nuclear Fuel Immune from Delayed Hydride Cracking during Dry Storage? - An IAEA Coordinated Research Programme
    C. Coleman and Z. He, Canadian Nuclear Laboratories, Chalk River, ON, Canada; V. Inozemtsev, International Atomic Energy Agency (IAEA), Vienna, Austria; V. Markelov, A.A. Bochvar Institute, Moscow, Russia; M. Roth, RATEN, Arges, Romania; V. Makarevicius, Lithuanian Energy Institute, Kaunas, Lithuania; J. K. Chakravartty, Bhabha Atomic Research Centre, Mumbai, India; A. M. Alvarez-Holston, Studsvik Nuclear, Nykoping, Sweden; A. K. Liaqat, Pakistan Institute of Nuclear Science and Technology, Islamabad, Pakistan; and R. Lagudi, Instituto de Pesquisas Energeticas e Nucleares, Sao Paulo, Brazil

    Hydride Reorientation in Zircaloy-4 Under Different States of Stress as Studied With in Situ X-Ray Diffraction
    M. N. Cinbiz, A. T, Motta, and D. Koss, Pennsylvania State University, University Park, PA, USA; M. Billone, Argonne National Laboratory, Argonne, IL, USA