Zirconium in the Nuclear Industry: 17th Volume

    Comstock Bob, Barbéris Pierre
    Published: 2015

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    This STP contains the 40 peer-reviewed papers – two papers were named Kroll winners – that were presented at the 17th International Symposium on Zirconium in the Nuclear Industry held in Hyderabad, Andhra Pradesh, India in 2013.

    A dominant theme in these papers is the role of hydrogen on the performance of zirconium alloy components. Issues discussed in this volume where performance was dominated by hydrogen included the following:

    • Failure of BWR fuel rods was attributed to the localization of hydrides following accelerated corrosion and subsequent cracking of the hydride lenses. Despite an extensive investigation, the cause of the accelerated corrosion was not definitively identified.

    • The growth of beta-quenched Zircaloy-2 BWR channels was driven late in life by accelerated hydrogen pickup that coincided with the dissolution of second phase particles.

    • As reorientation of hydrides plays an important role during dry storage, in-situ measurements were performed to gain new insights into the reorientation of hydrides in Zircaloy-4.

    • Delayed hydride cracking (DHC) growth rate of in-service Zr-2.5Nb CANDU pressure tubes was controlled by thermal and irradiation effects on the microstructure (e.g, decomposition and reconstitution of the beta phase controlling hydrogen diffusion to the crack tip).

    In addition to papers that highlight the impact of hydrogen, several papers focus on understanding the mechanisms of hydrogen ingress into the metal or understanding the interaction of hydrogen with point defects and dislocation loops in the matrix.

    Table of Contents

    Reflections on the Development of the “f” Texture Factors for Zirconium Components and the Establishment of Properties of the Zirconium–Hydrogen System
    Kearns J.

    Displacive and Diffusional Transformations of the Beta Phase in Zirconium Alloys
    Banerjee S.

    Effect of Hydrogen on Dimensional Changes of Zirconium and the Influence of Alloying Elements: First-Principles and Classical Simulations of Point Defects, Dislocation Loops, and Hydrides
    Adamson R., Cantonwine P., Christensen M., Freeman C., Hallstadius L., Mader E., Wimmer E., Wolf W.

    Phase Field Modeling of Microstructure Evolution in Zirconium Base Alloys
    Chakraborty S., Choudhuri G., Dey G., Shah B., Srivastava D.

    Thermodynamics of Zr Alloys: Application to Heterogeneous Materials
    Barberis P., Fremiot P., Guerin P., Vauglin C.

    Influence of Sn on Deformation Mechanisms During Room Temperature Compression of Binary Zr–Sn Alloys
    Dey G., Leo Prakash D., Mani Krishna K., Preuss M., Quinta da Fonseca J., Saibaba N., Srivastava D.

    Impact of Iron in M5TM6
    Barberis P., Hoffmann P., Kaczorowski D., Mardon J., Stevens J.

    Microstructure and Properties of a Three-Layer Nuclear Fuel Cladding Prototype Containing Erbium as a Neutronic Burnable Poison
    Aubin J., Bourdiliau B., Brachet J., Doriot S., Guilbert T., Hamon D., Joubert J., Jourdan J., Mascaro A., Olier P., Raepsaet C., Toffolon-Masclet C., Tupin M., Urvoy S., Vandenberghe V.

    Characterizing Quenched Microstructures in Relation to Processing
    Barberis P., Gaillac A., Montheillet F., Piot D., Tran M.

    Identification of Safe Hot-Working Conditions in Cast Zr-2.5Nb
    Banerjee S., Chakravartty J., Jha S., Kapoor R., Kumar V., Saibaba N., Sarkar A.

    A Numerical Study of the Effect of Extrusion Parameters on the Temperature Distribution in Zr–2.5Nb
    Dey G., Jha S., Keskar N., Mani Krishna K., Raizada V., Saibaba N., Srivastava D., Vaibhaw K.

    Study on Effect of Processing on Texture Development in Zirconium-2.5 % Niobium Alloy Tubes
    Babu C., Ganesha G., Itisri K., Jha S., Kapoor K., Mistry R., Prahlad B., Rao S., Saibaba N.

    Numerical Modeling of Fuel Rod Resistance Butt Welding
    Bay F., Carcey-Collet D., Duthoo D., Gaillac A., Mocellin K., Vauglin C.

    Application of Coating Technology on Zirconium-Based Alloy to Decrease High-Temperature Oxidation
    Kim H., Kim I., Koo Y., Park J.

    Oxidation Mechanism in Zircaloy-2—The Effect of SPP Size Distribution
    Andrén H., Dahlbäck M., Hallstadius L., Ivermark M., Josefsson B., Sundell G., Tejland P., Thuvander M.

    Effect of Sn on Corrosion Mechanisms in Advanced Zr-Cladding for Pressurised Water Reactors
    Ambard A., Blat-Yrieix M., Comstock R., Cottis R., Forsey A., Francis E., Frankel P., Grovenor C., Hallstadius L., Lozano-Perez S., Lyon S., Moat R., Ni N., Preuss M., Wei J.

    Understanding of Corrosion Mechanisms of Zirconium Alloys after Irradiation: Effect of Ion Irradiation of the Oxide Layers on the Corrosion Rate
    Ambard A., Blat M., Bossis P., Cuisinier D., Hamann J., Jomard F., Kaczorowski D., Miquet A., Tupin M.

    Effect of Alloying Elements on Hydrogen Pickup in Zirconium Alloys
    Comstock R., Couet A., Motta A.

    Toward a Comprehensive Mechanistic Understanding of Hydrogen Uptake in Zirconium Alloys by Combining Atom Probe Analysis With Electronic Structure Calculations
    Andrén H., Hallstadius L., Lindgren M., Panas I., Sundell G., Thuvander M.

    Corrosion and Hydrogen Uptake in Zirconium Claddings Irradiated in Light Water Reactors
    Abolhassani S., Bart G., Bertsch J., Grosse M., Hallstadius L., Hermann A., Kuri G., Ledergerber G., Lemaignan C., Martin M., Portier S., Proff C., Restani R., Valance S., Valizadeh S., Wiese H.

    Oxidation and Hydrogen Uptake of ZIRLO Structural Components Irradiated to High Burn-Up
    Aulló M., Culebras F., García-Infanta J., Garde A., Schrire D.

    Performance and Property Evaluation of High-Burnup Optimized ZIRLO™ Cladding
    Atwood A., Garde A., Pan G.

    Corrosion, Dimensional Stability and Microstructure of VVER-1000 E635 Alloy FA Components at Burnups up to 72 MWday/kgU
    Kobylyansky G., Markelov V., Nikulina A., Novikov V., Novoselov A., Obukhov A., Peregud M., Shevyakov A., Shishov V., Volkova I.

    Corrosion and Hydriding Model for Zircaloy-2 Pressure Tubes of Indian Pressurised Heavy Water Reactors
    Sinha R., Sinha S.

    Oxide Surface Peeling of Advanced Zirconium Alloy Cladding after High Burnup Irradiation in Pressurized Water Reactors
    Pan G., Garde A., Hallstadius L., Mueller A.

    The Effects of Microstructure and Operating Conditions on Irradiation Creep of Zr-2.5Nb Pressure Tubing
    Bickel G., Griffiths M., Walters L.

    Breakthrough in Understanding Radiation Growth of Zirconium
    Barashev A., Golubov S., Singh B., Stoller R.

    Microstructural Evolution of M5TM7 Alloy Irradiated in PWRs up to High Fluences—Comparison With Other Zr-Based Alloys
    Béchade J., Cloué J., Doriot S., Gilbon D., Legras L., Mardon J., Menut D., Miquet A., Verhaeghe B.

    Modeling Irradiation Damage in Zr-2.5Nb and Its Effects on Delayed Hydride Cracking Growth Rate
    Bickel G., Buyers A., Chaput H., Coleman C., Griffiths M.

    Understanding the Drivers of In-Reactor Growth of β-Quenched Zircaloy-2 BWR Channels
    Dahlbäck M., Hallstadius L., Ivermark M., Ledergerber G., Romero J.

    Impact of Hydrogen Pick-Up and Applied Stress on C-Component Loops: Toward a Better Understanding of the Radiation Induced Growth of Recrystallized Zirconium Alloys
    Béchade J., Cloué J., Feaugas X., Gilbon D., Mardon J., Onimus F., Tournadre L.

    Contribution to the Study of the Pseudobinary Zr1Nb–O Phase Diagram and Its Application to Numerical Modeling of the High-Temperature Steam Oxidation of Zr1Nb Fuel Cladding
    Adámek J., Burda J., Klouček V., Krejčí J., Linhart S., Lorinčík J., Négyesi M., Novotný L., Přibyl A., Siegl J., Sopoušek J., Vrtílková V.

    Experimental Comparison of the Behavior of E110 and E110G Claddings at High Temperature
    Hózer Z., Horváth M., Kemény T., Kunstár M., Nagy I., Novotny T., Perez-Feró E., Pintér-Csordás A., Vimi A.

    Effect of Pre-Oxide on Zircaloy-4 High-Temperature Steam Oxidation and Post-Quench Mechanical Properties
    Desquines J., Duriez C., Grandjean C., Guilbert S., Lacote P., Montigny G.

    Deviations From Parabolic Kinetics During Oxidation of Zirconium Alloys
    Grosse M., Steinbrück M.

    Influence of Steam Pressure on the High Temperature Oxidation and Post-Cooling Mechanical Properties of Zircaloy-4 and M5 Cladding (LOCA Conditions)
    Brachet J., Cabrera A., Crébier P., Gilbon D., Jacques P., Le Saux M., Mardon J., Vandenberghe V.

    Analysis of the Secondary Cladding Hydrogenation During the Quench–LOCA Bundle Tests With Zircaloy-4 Claddings and its Influence on the Cladding Embrittlement
    Grosse M., Kaestner A., Roessger C., Steinbrueck M., Stuckert J., Walter M.

    Effect of Hydride Distribution on the Mechanical Properties of Zirconium-Alloy Fuel Cladding and Guide Tubes
    Chen J., Kuo R., Yagnik S.

    Mechanisms of Hydride Reorientation in Zircaloy-4 Studied in Situ
    Almer J., Colas K., Daymond M., Motta A.

    Hydriding Induced Corrosion Failures in BWR Fuel
    Cheng B., Dunavant R., Kucuk A., Lemons J., Lin Y., Lutz D., Schneider R., Yeager H.

    Author and Subject Index

    Committee: B10

    DOI: 10.1520/STP1543-EB

    ISBN-EB: 978-0-8031-7580-8

    ISBN-13: 978-0-8031-7529-7

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