B10 2019 Zirc Presentations

    Papers

    Quantifying Processing Map Uncertainties by Modelling the Hot Compression Behavior of a Zr-2.5Nb Alloy
    C. Daniel, C. Peyton, and J. Quinta da Fonseca, The University of Manchester, Manchester, UK.
    P. Jedrasiak, and H. Shercliff, University of Cambridge, Cambridge, UK P. Honniball.
    L. Bradley, Rolls-Royce plc, Derby, UK

    Fabrication of E110 Alloy Fuel Rod Claddings on Electrolytic Zirconium Base with Removing Fluorine Impurity for Providing Resistance to Breakaway Oxidation in High-Temperature Steam
    V. Markelov, A. Malgin, N. Filatova, V. Novikov, A. Shevyakov, A. Gusev, I. Shelepov, and A.V. Golovin, VNIINM, Russia
    A. Ugryumov, and A. Dolgov, TVEL, Russia, A. Ziganshin, JSC “ChMP”, Russia, V. Donnikov, and V. Latynin, JSC “VTI”, Russia

    Ceramic Coatings for Nuclear Cladding to Increase Accident Tolerance
    E. Alat, D.E. Wolfe, and A.T. Motta The Pennsylvania State University, University Park, PA, USA
    J. Hu, Argonne National Laboratory, IL, USA

    Coating Technology on the Zirconium Alloy Cladding for Enhanced Accident Tolerant Fuel
    H-G Kim, I-H Kim, Y-I Jung, D-J Park, J-H Park, Y-H Lee, and B-K Choi, Korea Atomic Energy Research Institute, Daejeon, Republic of Korea

    The Behavior of CR-Coated Zirconium Alloy Cladding Tubes at High Tempuratures
    N. Chaari, J. Bischoff, and C. Delafoy, Framatome, Lyon, France.
    P. Barbéris, Framatome, Ugine, France. K. Nimishakavi, Framatome, Lynchburg, VA, USA

    Effects of Cold Spray Chromium Coatings on the Properties of Zirconium Alloys
    J. Romero, and J. Walters, Westinghouse Electric Company, Hopkins, SC, USA. S. Kachur, A. Mueller, J. Partezana, W. Byers, and G. Wang, Westinghouse Electric Company, Churchill, PA, USA

    Effect of Loading Direction on Slip and Twinning in an Irradiated Zirconium Alloy
    R. Thomas, D. Lunt, M. Atkinson, J. Quinta da Fonseca, M. Preuss, and P. Frankel, University of Manchester, Manchester, UK.
    F. Barton, and J. O’Hanlon, Rolls-Royce plc, Derby, UK

    Full Scale Fracture Toughness Behavior of Zr-2.5Nb Pressure Tubes with High Hydrogen Concentrations and Different Hydride Morphologies
    J. Cui and G. Shek, Kinectrics Inc., Toronto, Ontario, Canada

    Deformation Mechanisms of Zirconium Alloys After Irradiation Studied by in situ Straining Experiments in TEM, Molecular and Dislocation Dynamics Simulations
    F. Onimus, L. Dupuy, M. Gaumé, and W. Kassem, Université Paris-Saclay, Gif-sur-Yvette, Cedex, France.
    F. Mompiou, CEMES CNRS and Université de Toulouse, Toulouse Cedex, France

    Test-Reactor Study of the Effect of Zirconia Coating of Inconel Spacer Cells on Shadow Corrosion
    C. Anghel, M. Limbäck, B. Andersson, and J. Wright, Fuel Materials Center of Excellence, Westinghouse, Västerås, Sweden.
    G. Westin, and M. Leideborg, Department of Chemistry - Ångström Laboratory, Uppsala University, Uppsala, Sweden.
    T. Tverberg, Institute for Energy Technology, Halden, Norway

    Influence of Hydrides upon the Fatigue Initiation Behavior of Irradiated Zircaloy-2
    P. Honniball, and C. Gee, Rolls-Royce plc, UK.
    L. Cogez, Canadian Nuclear Laboratories, Chalk River, Ontario, Canada

    Measurement of In-reactor Stress Relaxation in Pre-irradiated Zirconium Alloys by Four-point Bend Technique
    S. Yagnik, Electric Power Research Institute, Palo Alto, CA, USA.
    I. Arimescu, Framatome, Richland, WA, USA.
    R. Adamson, Zircology Plus, Fremont, CA, USA.
    G. Kobylyansky, S. Seryodkin, and A. Obukhov, SC “SSC RIAR”, Russia

    Ex-situ and In-situ Studies of Radiation Damage Mechanisms in Zr-Nb Alloys
    J. Liu, G. He, A. Callow, K. Li, S. Lozano-Perez, A. Wilkinson1, M. Moody, and C. Grovenor, Oxford University, Oxford, UK.
    J. Hu, M. Kirk, and M. Li, Argonne National Laboratory, Argonne, IL, USA.
    A. Mir, J. Hinks, and S. Donelly, University of Huddersfield, Huddersfield, UK.
    J. Partezana, Westinghouse Electric Company, Pittsburgh, PA, USA.
    H. Nordin, Atomic Energy of Canada Limited, Chalk River, Ontario, Canada

    Towards an Improved Understanding of the Mechanisms Involved in the Increased Hydrogen Uptake and Corrosion at High Burnups in Zirconium-based Claddings
    S. Abolhassani, A. Baris, R. Vanta, J. Hawes, R. Grabherr, A. Colldeweih, R. Restani, A.Hermann, J. Bertsch, M. Chollet, G. Kuri, M. Martin, S. Portier, H. Wiese, H. Schweikert, and G. Bart, Laboratory for Nuclear Materials, Nuclear Fuels Group, NES, and AHL, NES, Paul Scherrer Institute, 5232 Villigen PSI, Switzerland.
    K. Ammon, and G. Ledergerber, Kernkraftwerk Leibstadt AG, CH-5325 Leibstadt, Switzerland. M. Limbäck, Westinghouse Electric Sweden AB, Västerås, Sweden

    Evaluation of Neutron Irradiated Additively-Manufactured Zircaloy-2
    J. Partezana, Westinghouse Electric Company LLC, Pittsburgh, PA, USA.
    P. Xu, and W. Cleary, Westinghouse Electric Company LLC, Columbia, SC, USA

    Corrosion and Deuterium Pickup in Zr-2.5Nb Twenty Years of In-Reactor Testing at the OECD Halden Boiling Water Reactor
    H. Nordin, Canadian Nuclear Laboratories, Chalk River, Ontario, Canada.
    R. Szőke, Institute for Energy Technology, Halden, Norway

    New Methodologies for High Resolution Mapping of Light Elements in Zirconium Oxide with SIMS
    C. Jones, K. Li, J. Liu, K. Moore, and M. Preuss, University of Manchester, Manchester, UK
    K. Li, J. Liu, T. Aarholt, and C. Grovenor, University of Oxford, Oxford, UK
    T. Aarholt, University of Oslo, Oslo, NO
    M. Gass,Wood plc, Warrington, UK
    K. Moore, Photon Science Institute, University of Manchester, Manchester, UK

    Investigating the Corrosion Behaviour of Zircaloy-4 in LiOH under a Thermal Gradient and Two Phase Flow Regime
    A. Panteli, F. Baxter, H. Hulme, M. Gass, A. Cole-Baker, and P. Binks, Wood plc, Warrington, UK
    J. Smith, and C. Miszkowska, Rolls-Royce plc, Derby, UK

    Effect of Ion Irradiation of the Metal on the Oxidation Rate of the M5Framatome Alloy
    M. Tupin, R. Verlet, K. Colas, M. Jublot, and G. Baldacchino, CEA Saclay, Gif-sur-Yvette, Cedex, France
    K. Wolski, CEA Saclay, Ecole des Mines de Saint Etienne, Cedex, France
    I. Idarraga, EDF SEPTEN, Lyon, France
    D. Kaczorowski, Framatome ANP, Lyon, France

    The Effect of Photon Irradiation on the Corrosion of Zirconium Alloys
    A. Couet, Y. He, T. Kim, M. Elbakhshwan, and L. He , University of Wisconsin, Madison, WI, USA
    K. Terrani, Oak Ridge National Laboratory, Oak Ridge, TN, USA
    S. Armson, S. Frankel, and M. Preuss, The University of Manchester, Manchester, UK

    Characterization of Long-Term, In-Reactor Zircaloy-4 Corrosion Coupons and the Impact of Flux, Fluence, and Temperature on Oxide Growth, Stress Development, Phase Formation, and Grain Size
    B. M. Ensor, and A.T. Motta, The Pennsylvania State University, University Park, PA, USA
    B. M. Ensor, Naval Nuclear Laboratory, Knolls Site, Schenectady, NY, USA
    G. Lucadam, J. R. Seidensticker, and R Bajaj, Naval Nuclear Laboratory, Bettis Site, West Mifflin, PA, USA
    Z. Cai, Advanced Photon Source, Argonne National Laboratory, Argonne, IL, USA

    Enhanced Hydrogen Uptake und Reaction Kinetics During Oxidation of Zircaloy-4 in Nitrogen Containing Steam Atmospheres
    M. Grosse, M. Steinbrück, and S. Pulvermacher, Karlsruhe Institute of Technology, Institute for Applied Materials, Karlsruhe, Germany
    B. Schillinger, Technische Universität München, München, Germany

    Zirconium Hydride Precipitation and Dissolution kinetics in Zirconium Alloys
    E. Lacroix, P.-C. Simon,and A.T. Motta, The Pennsylvania State University, University Park, PA, USA
    J.D. Almer, Argonne National Laboratory, Lemont, IL, USA

    Zirconium-Applied Anisotropic Cluster Dynamics for Irradiation Induced Dfect Modeling in Presence of Hydrogen
    N. Chaari, and F. Bourlier, Framatome, Lyon, France
    D. Brimbal, Framatome, La Defense, France
    P. Barberis, Framatome, Ugine, France

    Understanding the Hydrogen Pickup Mechanisms Under Irradiation Effect of Ion Irradiation of the Oxide and the Metal on the Hydrogen Pickup Rate of M5Framatome
    B. Queylat, M. Jublot, and M. Tupin, CEA-DEN, Service d’Études des Matériaux Irradiés, CEA, Université Paris-Saclay, F-91191, Gif-sur-Yvette Cedex, France
    F. Martin, Den-Service de la Corrosion et du Comportement des Matériaux dans leur Environnement (SCCME), CEA, Université Paris-Saclay, F-91191, Gif-sur-Yvette, France

    Micro-mechanical Characterization of Hydrides in Zr-2.5 wt% Nb Pressure Tube Material
    V. Bhakhri, W. Li, C. Howard, S. Hanlon, C. Dixon, C. Mayhew, C. Judge, and S. St. Lawrence, Canadian Nuclear Laboratories, Chalk River, Ontario, Canada

    Fundamental Understanding of Nb Effect on Corrosion Mechanisms of Zr-Nb Alloys In and Out of Reactor
    Z. Yu, M. Moorehead, L. Borrel, and A. Couet, University of Wisconsin, Madison, WI, USA
    J. Hu, Argonne National Laboratory, Argonne, IL, USA
    M. Bacchav, Idaho National Laboratory, Idaho Falls, ID, USA

    A Fast Efficient Multi-scale Approach to Modeling the Development of Hydride Microstructures at the Component Level in Zirconium Alloys
    M. Patel, L. Reali, A. Sutton, D. Balint, and M. Wenman, Imperial College London, London, UK

    Influence of Thermal-mechanical Cycling on Pre-hydrogenated Zircaloy-4 Embrittlement by radial Hydrides
    J. Desquines, and S. Charbaut, IRSN, Saint-Paul-Lez-Durance, France
    M. Puls, MPP Consulting, Oakville, Ontario, Canada
    M. Philippe, IRSN, Fontenay-aux-Roses, France

    Fracture of Gamma and Delta Hydrides during Delayed Hydride Cracking
    S. Hanlon, C. Coleman, and A. Buyers, Canadian Nuclear Laboratories, Chalk River, Ontario, Canada
    G. McRae, Carleton University, Ottawa, Ontario, Canada

    On the Nature of the Breakaway Corrosion Phenomenon during Zr and Zr Alloy Oxide Growth
    B. M. Ensor, A. Lucente, and J. Seidensticker1, Naval Nuclear Laboratory, Knolls Site, Schenectady, NY, USA
    A. T. Motta, The Pennsylvania State University, University Park, PA, USA
    J. Partezana, Westinghouse Electric Company LLC, Pittsburgh, PA, USA
    Z. Cai, Argonne National Laboratory, Lemont, IL, USA

    Characterization of Hydrides and the α-Zr Matrix in Zirconium Alloys Effects of Stresses, Microstructure and Neutron Irradiation on Hydride Texture, Terminal Solid Solubility and Dislocation Structure
    P. Vizcaíno, and A. Flores, Centro Atómico Ezeiza, CNEA, Buenos Aires, Argentina
    M. Vicente, J. Santisteban, A. Tolley, and A. Condó, Centro Atómico Bariloche, CNEA, Bariloche, Argentina
    G. Domizzi, Centro Atómico Constituyentes, CNEA, Buenos Aires, Argentina
    J. Almer, Advanced Photon Source, Argonne National Laboratory, Argonne, IL, USA

    Experimental Simulation of the Behavior of E110 Claddings Under Accident Conditions Using Electrically Heated Bundles
    Z. Hózer, I. Nagy, R. Farkas, N. Vér, M. Horváth, Z. Kis, B. Maróti, and L. Szentmiklósi, Hungarian Academy of Sciences Centre for Energy Research, Budapest, Hungary
    P. Holecz, G. Auguszt and G. Gémes, TÜV Rheinland InterCert Ltd., Budapest, Hungary

    Development of Thermokinetic Tools for Phase Transformation Studies of Zr Alloys in Service and LOCA Conditions
    C. Toffolon-Masclet, L. Martinelli, J. C. Brachet, and F. Legendre, DEN-Service de Recherches Métallurgiques Appliquées, CEA, Université Paris-Saclay, Gif-sur-Yvette, France
    C. Desgranges, DEN-Service de la Corrosion et du Comportement des Matériaux dans leur Environnement, CEA, Université Paris-Saclay, Gif-sur-Yvette, France
    P. Lafaye, Safran-Tech, rue des jeunes bois, Châteaufort, Magny les hameaux, France
    J-C Crivello, J-M Joubert, and D. Monceau, Centre for Research in Computational Thermochemistry (CRCT), Department of Chemical Engineering, Polytechnique Montréal, Montréal, Québec, Canada

    Analysis of the Corrosion Behaviour of Vapour-Deposited CrN Coated Zirconium under Normal Operation and Accident Scenarios
    C. Dever, and H. Nordin, Canadian Nuclear Laboratories, Chalk River, Ontario, Canada
    K. Daub, Queen’s University, Kingston, Ontario, Canada

    Furthering the Mechanistic Understanding of the Corrosion of Zr Alloys via Multiscale Microstructural Analysis
    S. Armson, A. Garne, M. Yankov, F. Baxter, C. Race, M. Preuss, and P. Frankel, The University of Manchester, Manchester, UK
    J. Smith, Rolls-Royce plc, Derby, UK
    F. Baxter, Wood. PLC, Birchwood, UK

    Results of the QUENCH-LOCA Experimental Program at KIT
    J. Stuckert, M. Große, M. Steinbrück, and M. Walter, Karlsruhe Institute of Technology, Karlsruhe, Germany
    A. Wensauer, PreussenElektra GmbH, Hannover, Germany

    Towards a Mechanistic Understanding of Pellet Cladding Interaction Using Advanced 3D Characterisation and Atomistic Simulation
    P. Frankel, A. Garner, A. Plowman, C. Gillen, C. Race, and J. Donoghue, The University of Manchester, Manchester, UK
    S. Hanlon and A. Phillion, Canadian Nuclear Laboratories, Chalk River, ON, Canada
    M. Daymond, Queen’s University, Kingston, ON, Canada
    C. Anghel, Westinghouse Electric Sweden AB, Västerås, Sweden
    A. Ambarde, EDF Research and Development, Materials and Mechanics of Components, Ecuelles, Moret-sur-Loing, France


    Posters

    M5 and Zy2 Breakaway During Simulated LOCA Test
    P. Barberis, C. Ly, and C. Linardon, Framatome, Ugine, France
    R. Zino, Framatome, Lyon, Saint-Etienne, France

    Shadow Corrosion - Experiments and Modeling
    P. Barbéris, Framatome, Ugine, France
    M. Skocic, Framatome, Le Creusot, France
    D. Kaczorowski, and D. Perche, Framatome, Lyon, France
    Y. Wouters, SIMaP / Université Grenoble Alpes, Saint-Martin-d’Hères Cedex, France
    K. Nowotka, Framatome GmbH, Erlangen, Germany

    Effects of Hydrogen Concentration and tempurature on the DHC Crack Growth Threshold Stress of Irradiated Electron Beam Welded Zircaloy
    R. Bentley,and C. Gee, Rolls-Royce plc, Derby, UK
    H. Chaput, Canadian Nuclear laboratories, Chalk River, Ontario, Canada

    Texture Development of the α and β Phases During hot-rolling of s Dual-phase Zr-2.5Nb Alloy
    P. Barbéris, Framatome, Ugine, France
    M. Skocic, Framatome, Le Creusot, France
    D. Kaczorowski, and D. Perche, Framatome, Lyon, France
    Y. Wouters, SIMaP / Université Grenoble Alpes, Saint-Martin-d’Hères Cedex, France
    K. Nowotka, Framatome GmbH, Erlangen, Germany

    Optimized Manufacture of Nuclear Fuel Cladding Tubes by Numerical
    A. Gaillac, P. Barbéris, and I. Crassous, Framatome Ugine, Ugine Cedex, France
    F. Lyonnet, Framatome Paimboeuf, Paimboeuf, France

    The Nature of Dislocation Loops in Proton Irradiated Zirconium Alloys
    H. Xu, R. Jones, A. Garner, S. Irukuvarghula, R. Hulse, T. Ungár, P. Frankel, and M. Preuss, University of Manchester, Manchester, UK
    M. Topping, Queen’s University, Kingston, Ontario, Canada
    G. Zilahi, G. Ribárik and T. Ungár, Eötvös Loránd University, Budapest, Hungary
    P. Kenesei, Advanced Photon Source, Argonne National Laboratory, Argonne, IL, USA
    C. Riley and P. Honniball, Rolls-Royce plc, Derby, UK

    Diffusion Path Comparison of the Hydrogenated Species in the Oxide Layers Formed on Zircaloy-4 and M5 in PWR Conditions
    M. Jublot, K. Colas, M. Tupin, and C. Bisor, CEA-DEN, Université Paris-Saclay, Gif-sur-Yvette Cedex, France

    Characterizing Fatigue Damage in Zr-2.5Nb
    H. Nordin, A. Phillion, and T. Karlsen, Canadian Nuclear Laboratories, Chalk River, Canada

    The Cause Of Transition In Fuel Cladding Oxidation Rates
    S. Ortner, M. Blackmur, H. Weekes, and H. Swan, National Nuclear Laboratory, Abingdon OX14 3DB, UK
    M. Fenwick, and M. Gass, Wood plc, Birchwood Park, Warrington, UK

    The Sensitivity in the Crack Growth Resistance of Irradiated Zr-2.5Nb to Small Changes in the Orientation of Hydrides
    S. St. Lawrence, Canadian Nuclear Laboratories, Chalk River, Ontario, Canada

    Oxide Stresses and Tetragonal Phase Distributions in Oxidised Zircaloy-4
    H Swan, M. Blackmur, P. Styman, H. Wilcox, and S. Ortner, National Nuclear Laboratory, Abingdon, UK
    S. Sherry, and F. Baxter, Wood plc, Birchwood Park, Warrington, UK
    J. Smith, previously Rolls-Royce plc, Raynesway, Derby, UK

    Linking Radiation Damage to Solute Segregation, Interdiffusion and Solubility in the Zr-Nb-Cr System
    V. Tuli, and P. Burr, The University of New South Wales, Sydney, Australia
    A. Jain, and D. Trinkle, University of Illinois at Urbana-Champaign, Urbana, IL, USA
    M. Wenman, Imperial College London, London, UK
    L. Messina, KTH Royal Institute of Technology, Stockholm, Sweden